ML20100A333
| ML20100A333 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/28/1995 |
| From: | Miller D DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20100A324 | List: |
| References | |
| PROC-951228, NUDOCS 9601050075 | |
| Download: ML20100A333 (231) | |
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. O DUKE POWER COMPANY Catawba Nuclear Station l i I i 1 l ASME Inservice Testing Program l
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Revision 23 June 1996 1 I i J i
\ j Prepared by: , . , a[ f// Date: /J-1d-9[
Reviewed by: h Date: /t/24[fJ' j Approved by:7f M Date: /MAY/94 l 9601050075 951228 PDR ADOCR 05000445 { p PDR j i
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- 1.0 Catawba Nuclear Station Program Document 1 - 34 l 4
2.0 Table of Abbreviations 1-2 i l 3.0 UNIT I IST PROGRAM 3.1 Pump Inservice Testing Program 1-2 a 3.2 Valve Inservice Testing Pr n, ram i Shared (YC & RN) .. .. . . . . . . ... . ..S H A R E D 1 - 1 l Steam Generator Blowdown Recycle . . . . . ..BB 1-1 l Auxiliary Feedwater System . .. .. . ..CA 1-2 Feedwater System . . ... . .. .... . . . . . . .. . . . . . . . . . . . ..CF 1-1 . Diesel Generator Engine Fuel Oil System .. .. . . . . . ..FD 1-1 Refueling Water System . . . .. . . . . . . . .. . ..FW 1-1 Instrument Air Lock ... .. ... . . . . . . . . ..lA 1-1 Component Cooling .. . ... .. . . ..KC 1-2 l Diesel Generator Engine Cooling Water System . ..KD 11 i f Spent Fuel Cooling . . . . . . . ..KF 1-1 l
\ Diesel Gen. Engine Lube Oil.. .. . . . . . . . ..LD 1-1 Radiation.. . . .. .. .. . .. . ..Mi 1-1 Boron Recyle .. .. . .. . .. .. . . ..NB 1-1 Reactor Coolant System.. . . ..NC 1-1 !
Residual Heat Removal.. . .. . ..ND 1-1 l Ice Condenser Refrigeration . . .. . . ..NF 1-1 l Safety injection System.. . .. . ...NI 1-4 i Nuclear Sampling System.. . . . . ..NM 1-1 l Containment Spray.. . . ..NS 1-1 l Chemical & Volume Control.. . . . . .. NV 1-2 ) Containment Penetration Valve injection Water System.. . ..NW 1-5 l Fire Protection System.. .. . . ..RF 1-1 l Nuclear Service Water System . . . . . ..RN 1-2 i Main Steam To Aux Equipment.. . . ..SA 1-1 ) Main Steam . . . ..SM 1-1 ' Main Steam to Atmosphere.. . . . ..SV 1-1 Breathing Air... . . . . . ..VB 1-1 Diesel Generator Engine Starting Air.. . . ..VG 1-2 ! Instrument Air System... . . ..VI 1-1 l Containment Purge Ventilation . . ..VP 1-1 ) Containment Air Release & Additional System.. . ..VQ 1-1 i Station Air System.. . . . . . ... ..VS 1-1 l Cont. Air Ret. & Hydrogen Skimmer System . . . ...VX 1-1 Cont. Hydrogen Sample & Purge System . ..VY 1-1 l
- Decontamination System . ..WE 1-1 Liquid Waste Recyle System .. . ..WL 1-1 b- Makeup Demineralizer Water System . . . . ..YM 1-1 Page I of 3
I 4 Table of Contents n (v) SECTION PAGES J 4.0 UNIT 2 IST PROGRAM
- 4.1 Pump Inservice Testing Program 1-2
. 4.2 Valve Inservice Testing Program Steam Generator Blowdown Recycle.. . .... .. ...... . . . . ...... . . ..BB 1-1 Auxiliary Feedwater System... ... ... . . . . . . . . . . . . . . . . . .. . ..CA 1-2 Feedw ater System..... .. ...... ... ... .. ... . . . . . . . . . . . . . . . . . ...CF 1-1 Diesel Generator Engine Fuel Oil System .. ....... .... . . . . . . ...FD 1-1 i Refueling Water System . . .... . . . . . . . . . . . . . . . . . . . . . . . . . . .. FW 1-1 -
Instrument Air Lock...... . .. ... . . . . . . . . .. ....... . ... . . . . . . .. . . . . . l A 1-1 ~ Component Cooling . .. . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . .. KC 1-2 Diesel Generator Engine Cooling Water System., .... .. .... .... . ..KD 1-1 1 Spent Fuel Cooling.. ... . . . .. .... ..... ... .. .. ....... . .. .. .. . . .. . . KF 1-1 l Diesel Gen. Engine Lube Oil...... .. . . . . .. . . . . . . . . . . . . ..LD 1-1 . Radiation. .. .. .. ...... . ..... . . . . .. . . . .. . . . . . . . . . . . . .... ..Mi 1-1 l Boron Recyle ........ .. . .. ...... . .. ... . . . . . . . . . . . . . . . . . ..NB 1-1 ,fy Reactor Coolant System. ... . .. .. ........ ... . . .. .. . . . . . ..NC 1-1
-(y Residual Heat Removal.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... ..ND 1-1 Ice Condenser Refrigeration.. ..... . .. .. . . . . . . . . . . . . . . . . . . ... .. N F 1-1 Safety injection System.. . . . . .... .... .. ...... .... ... . .. .. .. . ..NI 1-4
, Nuclear Sampling System.... .. .... . .. ...... . . . . . . . . . . . . . ....NM 1-1 Containment Spray.. ... . . . . . . . . . . . . . .. . . . ..NS 1-1 Chemical & Volume Control.. ...... . . ... . . . . . . . . . . . . . . . NV 1-2 Containment Penetration Valve injection Water System... . . . .. .. NW 1-4 , Fire Protection System.. . . . . . . . . . . . . . . . . . . . . . . . . . . ..RF 1.1 Nuclear Service Water System .. . . . .. .. . .... .. . .. .... . . ....RN 1 - I. l Main Steam To Aux Equipment... .. .. .. .. .. ..... .. . . . . . . . ..SA 1-1 Main Steam . .... . .. . .. . . . . . . . . . . . . . . . . . . . . . ..SM 1-1 ^ Main Steam to Atmosphere . . . . . . . . . . . . .. . . . . . . . SV 1-1 Breathing Air.. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .VB 1-1
- Diesel Generator Engine Starting Air.. . . . . . . . . . . . . ..VG 1-2 Instrument Air System... . . . . . . . . . . ..... .. . . . . . ..V1 1-1 n Containment Purge Ventilation.. .. . .. . .. . . . . .. . .... . . . . . . .VP 1-1 Containment Air Release & Additional System... .. . . . ..VQ 1-1 Station Air System.... ... . . . . . . . . . . .. . . . . . . . . . .. ..VS 1-1 Cont Air Ret. & Hydrogen Skimmer System.. . . . . . . . . . . . . . . . ..VX 1-1 Cont. Hydrogen Sample & Purge System.. .. . . . . .. ..VY 1-1 Decontamination System... . . . . ... . . . . . . . . . . . . . ..WE 1-1
- Liquid Waste Recyle System..... .. . . . . . . . . . . . . . . . . ..WL 1-1 Makeup Demineralizer Water System.. ... .. .. . .. . . . . . . . ..YM *1 - 1
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. Table of Contents O
v : SECTION PAGES
. 5.0 - ' RELIEF REQUEST 5.1 Pumps - Generic Relief Request 1-1 5.2 Pumps - Specific Relief Request 1-1
' 5.3 ' Valves - Generic Relief Re' quest 1-1
- 5.4 Valves - Specific Relief Request 1-1' 6.0 JUSTIFICATION FOR DEFERRAL 6.1 Valves - Justification for Deferral 1-1
.7.0 - Correspondence 1
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O CATAWBA NUCLEAR STATION ASME Section XI in-Service Testing Program Document i J i December 1995 i i !O i i . Prepared by: od/M. Date: /2/19 !1a' l Reviewed by: kmd,d. -////64- Date: /2 vofff l Approved by: 7~6 Date: /2/2r/95
- O
. t TABLE OF CONTENTS
,f r 1.0 ' Scope of Document
- (. . - 2.0 References
. 3.0 Definitions and Terms 40 Valve Program 4.1 Valve IST Program Scope 4.2 Exemption and Position Statements 4.3 Check Valve Testing 4.3.1 Test frequency 4.3.2 Leak Testing 4.3.3 Full Stroke Testing (Open and Close) 4.3.4 Partial Stroke Testing 4.3.5 Sample Disassembly 4.3.6 Use of Non-Intrusive Testing Techniques (NITS) 4.4 Relief Valve Testing 4.5 Leak Rate Testing 4.5.1 Appendix J (Containment isolation Valves) 4.6 Remote Position Indication and Testing From Remote Locations 4.7 Post Maintenance and Modification Testing (Retest) 4.8 Fall-Safe Testing j i
4.9 Skid-Mounted Valves ! I 4.10 Valve Test Acceptance Criteria l 4.10.1 Valve Stroke-Time Acceptance Criteria l 4.10.2 Stroke-Time measurements and methods 4 4.10.3 Limiting Values for Stroke-Time Acceptance Criteria ) 4.10.4 Engineering Evaluations 5.0 Pump Program 5.1 Pump IST Program Scope j 5.2 Exemption and Positior) Statements 2 5.3 Mini-flow and Full Flow Testing 7 5.4 Vibration Monitoring 4 5.4.1 Pump Drivers 5.4.2 Smooth Running Pumps 5.4.3 Vibration Points and Trending < CNS ASME in-service Testing Program Rev. 00 Page 2 of 34 CNSSCOPE. DOC 12/14/95
i I l I i \ i TABLE OF CONTENTS n 5.0 Pump Program (continued) a . 5.5 Testing From Remote Locations 5.6 Post Maintenance and Modification Testing (Retest) 5.7 Skid-Mounted Pumps ! 5.8 Test Acceptance Criteria 5.0.1 Pump Hydraulic Acceptance Criteria 6.0 Relief Request 1 6.1 Implementation of Relief Request i l 6.2 Interim Relief Request ! 7.0 Justification for Deferrais 7.1 Testing Deferral Justifications (Practicality Determinations) 8.0 Appendices i Appendix A: IST Program Responsibilities
\ Appendix B Supplemental Testing Program Appendix B: l , 1
- Appendix C: Notification of Program Changes 9.0 Enclosures i Enclosure 9.1: Revising the Program Enclosure 9.2: Program Bases Philosophy Enclosure 9.3: Valve Data Sheet 1
Enclosure 9.4: Pump Data Sheet Enclosure 9.5: Generic Relief Request Form
! Enclosure 9.6: Justification for Deferral Form i I
Enclosure 9.7: Specific Relief Request Form Enclosure 9.8: System Piping Classification Correlation Enclosure 9.9: Summary of CNS IST Program 10 yr. Submittal Changes c ( ( CNS ASME In-service Testing Program Rev. 00 Page 3 of 34 CNSSCOPE. DOC 12/14/95
4 1.0 SCOPE OF DOCUMENT b Technical Specification 4.0.5 requires performance of pump and valve testing in accordance with ASME Section XI. Failure to meet the requirements of this program is a violation of Technical
- Specifications and 10CFR 50.55a.
The purpose of this program document is to speciF; ihe C&'swba Nuclear Station (or hereafter referred to as " licensee" or "CNF") In-Sente Tasting program 'or performing valve and pump testing. This document will also outlins the process for additions, changes, and deletions of pumps and valves from the CNS IST prcgram. 1.1 Program Period: Second Ten-Year Interval (120 month period beginning August 19,1995); Unit (s) 1 and 2 Concurrently 1.2 Applicable ASME Code (s) and Addenda: i ASME/ ANSI OM 1987 Edition; PART 6 including OMb-1989 l ANSI /ASME OM-1 1987 ASME/ ANSI OM-1987 Edition; PART 10 including OMa-1988 i 1.3 Program Changes: ' 1 The NRC will be notified of IST program changes. However, component additions and O . deletions will be submitted and testing implemented or deleted without prior NRC V approval. In the instance where a component has been added to the IST program, testing and the appropriate program changes will take place within 90 days of revising the ; program source docurrents unless determined to be impractical. If a hardship is i identified, notification will be submitted to the NRC and an interim extension from testing implementation obtained. The content of this program document is for non-mandatory compliance to recommendations stated in NUREG-1482 and is intended for the purpose of maintaining program continuity and documenting additional discussions and positions relative to code interpretations. Therefore, changes to this program document will not require prior NRC l review and/or approval unless the licensee determines a need to do so. i CNS ASME In-service Testing Program Rev.00 Page 4 of 34 CNSSCOPE. DOC 12/14/95
2.0 REFERENCES
( t The following documents were used as references in the development of this document: 4 i Generic Letter 89-04 Generic Letter 89-10 10 CFR 50, Appendix B l 10 CFR 50.55a ASME OM-6 (OMb-1989), OM-10 (OMa-1988), and OM 1 (1987) Technical Specifications , Final Safety Analysis Report (FSAR) Nuclear System Directive: 408. Post-Maintenance Testing l Non-Mandatorv
References:
NUREG/CP-0123, Proceedings of the NRC/ASME Symposiums on Pump and Valve Testing NUREG-1482, Guidelines foi In-service Testing at Nuclear Power Plants, April 1995 ANSI OM-1,1981 Req. for in-service Testing of Nuclear Power Plant Pressure Relief Devices. OM-13, " Standard for Assessing the Operational Readiness for Power Operated Relief Valves." OM-22, " Standard for Assessing the Operational Readiness for Check Valves." ASME OMc CODE-1994 i 4 4 CNS ASME In-service Testing Program Rev.00 Page 5 of 34 CNSSCOPE. DOC 12/14/95
3.0 DEFINITIONS and TERMS (D V Generic Letter 89 the NRC letter providing additional requirements in testing MOVs to design basis conditions. Generic Letter 89 the NRC letter providing supplemental guidance on developing and enhancing plant IST programs. ASME Section XI- the section of ASME Codes and Standards Manual that determines how to perform in-service testing of light water reactor nuclear plant components. 4 ASME OM-10 Code - the part of Section XI codes dealing with the in-service testing of valves. i ASME OM-6 Code - the part of Section XI codes dealing with the in-service testing of pumps. Frequencies - the interval of time between in-service testing of the components. These intervals are defined in CNS Technical Specifications 4.0:
- 1) Quarterly (3 months)- 115 days maximum
- 2) Cold Shutdown (CSD)- Average Coolant Temperature (Tavg) 5 200'F 1
- 3) Refueling (RF) - Unit at shutdown for the purpose of replacing or rearranging all or a portion of the fuel assemblies or control rods.
p IST Component- components (valves and pumps) that are required to be tested per ASME Section XI. Sections 4.1 and 5.1 of this document define the criteria to be included in the (] IST program.
" App. B Component"- components (valves and pumps) tested under of 10CFR50, Appendix B.
" App. J Component" - components leak tested for containment integrity under 10CFR50, Appendix J. !
Active Component - a cornponent that must perform a mechanical motion during the course of , accomplishing a system safety function. l l Passive Component - a component that does not perform a mechanical motion during the course of I l accomplishing a system safety function. System Resistance- the hydraulic resistance to flow in a system Trending- a comparison of current data to previous data obtained under similar conditions j for the same equipment. Set Point - the value for which relief valves are set to relieve pressure. Leak Test - testing of valves to verify seat leakage is limited to a specified maximum. l l l CNS ASME In-service Testing Program Rev. 00 Page 6 of 34 CNSSCOPE. DOC 12/14/95 l
3.0 DEFINITIONS and TERMS (continued) { Stroke-Time - the time interval from valve actuation to the limit switch indication light at the end of the actuating cycle. Limiting Stroke-Time - the maximum time allowed for a valve to stroke before becoming immediately inoperable, i Relief Requests - A request submitted to the NRC requesting relief from the requirements of the Code for testing a particular component or a generic group of components. Justif. for Deferrals - A documented explanation of why a valve can only t>e tested at a cold shutdown or refueling outage frequency as opposed to quarterly. 1 4 i
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4 4 5 l l i l 4 l I O CNS ASME In-service Testing Program Rev.00 Page 7 of 34 CNSSCOPE. DOC 12/14/95
4.0 VALVE PROGRAM b 4.1 In Service Testing (IST) Program As required by 10CFR50.55a, valves that are classified in accordance of NRC Regulatory Guide 1.26 as ISI Class A, B, or C, which corresponds to ASME Class 1,2, or 3 respectively, are included in the CNS IST Program. The following defines the criteria for inclusion of equipment in the IST Program: a) All Category A valves that fall within the Duke ISI Class A, B, or C boundaries.
! b) All Category B and C valves that fall within the Duke ISt Class A, B, or C boundaries and are active in the mitigation of the Design Basis' Accidents (Design Basis Accidents are defined as those described in Chapter 15 of the FSAR).
4 c) Valves in systems specifically required by Technical Specifications to be tested per ASM5 Section XI. CNS has some valves that are active in certain non-Design Basis Events, are cold shutdown valves not assc: lated with an FSAR Chapter 15 event, are significant to plant safety, or are of economic importance i that are beyond the scope of 10CFR50.55a. Such valves will be tested in the supplemental,10CFR50 Appendix B Program. See Appendix B of this document for a discussion of this program. The scope of the OM Standards and Code has not been expanded to include all safety-related pumps and f; valves in the IST program. Until the scope of 10CFR50.55a is changed, the scope of the IST program will continue to include only those components within the Code classes unless otherwise determined by the
! licensee (reference NUREG-1482).
d i 2 4.2 Valve Testing Program Exemptions and Position Statements Vaives tested under jurisdiction of this program will be tested per requirements of OM-10 (OMa-1988), at the specified frequencies unless it has been determined to be impractical. This section of the p'rogram l document provides CNS positions on interpretations, guidance and other options regarding testing l altematives. I 1 j 4.2.1 Category A and A/C valves (containment and pressure isolstion valves) will be leak tested j in accordance with OM-10 (OMa-1988) section 4.2.2.3 and 10CFR50 Appendix J. i l l 4.2.2 Valve stroke times will be recorded to at least the nearest second, except for valves which have stroke times of less than one second. For these valves, a time of one second will be -
- recorded. Valves that stroke in less than 2 seconds may be exempted from reference ranges and the maximum limiting stroke time shall be 2 seconds as specified by OM-10 section 4.2.1.8 (e). Additionally, documented stroke times wil! be to the nearest full second.
- 4.2.3 Stopwatches used to measure stroke times will be calibrated annually, i .
4.2.4 OM 10, section 6.3 (h) requires the signature of the person or persons responsible for conducting and analyzing the test. The dated initials of the person or persons responsible for conducting and analyzing the test may be used in place of a signature in the record of a v/ the tests. Initials can be used as signatures to meet the intent of the OM-10 as long as somewhere in the test procedure the initials are identified by a full signature. CNS ASME In-service Testing Program Rev. 00 Page 8 of 34 CNSSCO'd. DOC 12/14/95
4.2 ' Valve Testing Program Exemptions and Position Statements (continued) t i 4.2.5 It is the licensee's position that valve testing will be deferred if the normal. code required [ test frequency or plant conditions would result in increased personnel risk or damage to j plant equipment. Practcality of such deferral shall be determined by the licensee and , i documented in the " Justification for Deferral" section of the IST Program manual. In such - cases, the licensee will not perform any type of destructive testing to determine the period of time at which damage to the equipment or risk to personnel would occur. Exercising , valves on a cold shutdown or refueling outage frequency is not a deviation from the code ! (reference NUREG-1482, Section 2.4.5).
- '4.2.6 Manual valves that meet the scope requirements of OM-10 or are taken credit for in the ;
_ safety analysis as capable of being repositioned to shut down the plant, to maintain the
- plant in a safe shutdown condition, or to mitigate the consequences of an accident will be
- - included in the IST program. However, testing of such valves will be so%ly based on
- exercising requirements established by the licensee.
j l 4.2.7 Valves that are not categorized as ISI Class A, B, or C need not be included in the IST Program. However, according to GL 89-04, Position 11. "The intent of 10 CFR 50 i Appendix A, GDC-1, and Appendix B, Criterion XI, is that all components, such as pumps { and valves, necessary for safe operation are to be tested to demonstrate that they will
- perform satisfactorily in service." The licensee reserves the right to include valves which e do not meet these criteria in the IST Program. These valves are typically tested in the Supplemental Program. In such cases, the licensee will specify how the component is l tested or if a deviation from the Code guidelines is allowable. CNS will not submit Relief Requests or Justification for Deferrals for "Non-Code"- Class valves.
f l ( 4.2.8 After valve maintenance, baseline stroke-times wdl be reset per OM-10, section 3.4. - 4.2.9 Thermal Relief Valves that meet the scope requirements of OM-10 or are taken credit for in the safety analysis for being capable of relieving pressure in code class 1,2 and 3 i piping systems by maintaining the plant in a safe shutdown condition, or in mitigating the
- consequences of an accident will be included in the IST program. However, testing of j such valves will be based on exercising frequencies established by the guidance given in OM PART 1,1987 sections 1.3.3 and 1.3.4. In the specific cases where check valves
- have been installed to provide thermal overpressurization protection, these check valves
! will be pressure tested to verify opening capability and NOT tested to verify set point or lift } pressure or will be replaced. I
- 4.2.10 Containment Purge Valves (VPs), which are passive in the closed direction, will be leak tested per 10 CFR 50, Appendix J but not stroke-timed for IST purposes. Containment
! Purge' valves are " passive" in Modes 1-4. During a postulated fuel handling accident inside the containment, no credit for containment isolation or mixing in the containment is i taken. System design assures a safe release path from the containment with the VP system in operation. The radiological consequences of a postulated fuel handling accident are within the exposure guideline values of 10CFR 100.
i 4.2.11 Containment Hydrogen Purge Valves (VY), which are passive in the closed direction,
- will be leak tested per 10 CFR 50, Appendix J but not stroke-timed for IST purposes.
. These valves are " passive" in Modes 1-4. CNS Technical Specifications requires i exercising these valves to the requirements of 4.0.5. However, power is removed and these valves are placed under administrative control as to not permit re-positioning after
'~.b they have been leak-tested per Appendix J. 3 CNS ASME In-service Testing Program 4- Rev.00 Page 9 of 34 CNSSCOPE. DOC 12/14/95 4
v . I l I-4.3 Check Valve Testing , i I Check valves tested under the jurisdiction of this program will be tested per Code requirements at the j specified frequencies unless it has been determined to be impractical. This secbon of the program 4 document is to provide the CNS positions concerning interpretations, guidance and other options and testing altematives for check valves. 4.3.1 For check valves in series where one of two valves is credited in the safety analysis, the verification that the pair of valves is capable of closing will be done on the basis of testing one of the check valves. l
- 4.3.2 Category A cnd A/C valves (containment and pressure isolation check valves) will be leak l l tested in accordance with OM-10 (OMa-1988) section 4.2.2.3, and 10CFR50 Appendix J.
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- 4.3.3 Full stroke testing of check valves will not necessarily constitute the obturator contacting )
the back-stop. Where possible, sufficient flow will be passed through the valve to verify design basis accident flow. If full flow is not possible, then the licensee will perform correlation testing, partial stroking, or other altematives as provided by OM-10 section , 4 4.3.3.3 Additionally, the code allows use of indirect evidence (such as system pressure, flow, temperature or level) or other positive means to verify flow or pressure , requirements. These indirect methods will not be subject to the range and accuracy I requirements of the code. (ref. NUREG-1482, section 4.1.2). Check valve exercising to verify the closed position will not require demonstrati.on that the valve was open prior to closure. 4.3.4 Seismic boundary check valves will be included in the program. i 4.3.5 Check valves included in the Sample Disassembly portion of the IST program will be disassembled and inspected under the provisions and guidelines given in GL 89-04 and per OM-10 (OMa-1988), section 4.3.2.4 (c). 4.3.6 Where applicable to the CNS IST program, back flow testing of check valves will be i performed in accordance with GL 89-04 guidance. Examples of methods that may be used to verify valve closure are as follows: l Pump discharge check valves - verified closed by meeting a parallel pump's acceptance criteria while cross-connected; Appendix J testing; 1
- Measure back flow through the valve using an open vent on the backside of the valve or ultrasonic flow measurement techniques; Pressure drop across a pump or or pump wind-milling.;
j Observation of extemalindication on valve stem; s a CNS ASME In-service Testing Program Rev. 00 Page 10 of 34 CNSSCOPE. DOC 12/14/95
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! - 4.3 ~ Check Valve Testing (continued) 1 4 4.3.7 As per recommendations stated in NUREG-1482, the licensee recognizes the NRC's j i . acceptance of non-intrusive techniques (N.I.T.) for testing ~ check valves. The licensee - l has purchased -N.I.T. equipment and is investigating incorporation into the testing l ' program. 'However, this N.I.T. equipment has only recently been introduced to the l industry and was not supphed from the vendor under the elements of the Q.A. program as ~ l l with other equipment utilized for testing safety related components. This places the
- burden on the licensee to validate the technology (e.g. software quahfications, calculation validity, engineering correlation, etc.). Therefore, it is the licensee's position that (N.I.T.)
l is a voluntary option and will be evaluated on a specific application basis if full stroke { [ exercising or sample disassembly cannot be performed. ; i i 4.4 Relief Valve Testing j i ! ! . Relief valves tested under the jurisdiction of this program will be tested per code requirements of OM-1, l 1987, unless it has been determined to be impractical. This section of the program document is to provide l 4 - the site's positions concoming interpretations, guidance, and testing attematives for relief valves. Relief I valves shall be considered for inclusion in the program if they provide overpressure protection for portions l of systems that perform a specific function in shutting down a reactor or in mitigating the consequences of ! an accident. 4.4.1 Relief valves that are not credited for assisting in mitigating the consequences of an
- accident and are only installed for over-pressure protection are considered passive.
4.5 Leak Rate Testing All category A valves will be tested per OM-10, section 4.2.2.2, except those valves which function in the
- course of plant operation in a manner that demonstrates adequate seat leak-tightness need not be leakage tested. In such cases (e.g., Containment Purge Isolation Valves) proper administrative controls will be implemented and the valves leak tested during refueling outages.
4.5.1 Category A containment isolation valves shall be tested per 10CFR50, Appendix J and a shall be included in the program per GL 89-04, Position 10. Where a valve is identified as
- a containment isolation valve in the Technical Specification or FSAR and if it is determined to be an " active" valve with respect to this function, it will be exercised to the
} closed position when there is an associated requirement for leak testing. ! 4.6 Testing from Remote Location i j Section 4.1 of OM-10 requires valves with remote position indication to be tested at least once every 2
- years to verify that the valve operation is accurately indicated. Valves that have remote operating j switches and/or power supplies shall also be tested and verified for proper indication from the remote
; location. Other valve operating parameters, such as timing will not be performed from the remote location during this testing.
1 4.7 Post Maintenance and Modification Testing (Retoot) (Reference Nuclear System Directive 408. Post-Maintenance Testing Seebons 408.9 and 408.10) 4 CNS ASME In-service Testing Program
, Rev.00 Page 11 of 34 CNSSCOPE. DOC 12/14/95
_y i l l 4.8 Fall-Safe Testing of Valves All Fail-Safe valves shall be tested in accordance with OM-10, section 4.2.1.6. Control valves are typically excluded from testing in the IST program. However, if a control valve must change position to support a safety-related function and it has a fail-safe position, then it must be included in the program and tested to venfy the ability to perform that function with power and/or air removed (or simulated power and/or air removal). 4.9 Skid-Mounted Valves
, Until the scope of components for 10CFR50.55a is expanded to include all safety-related pumps and valves, and until the OM codes and standards specifically address skid-mounted components, the testing of the ' major' components supported by skid mounted equipment will be an acceptable means for verifying the operational readiness of the skid-mounted equipment sub-components and assemblies. The licensee however, may opt to include certain components contained on these skids in the IST program for testing and trending purposes. In such cases, the licensee will not be obligated to submit Relief Request or Justification for Deferrals on testing alternatives nor will it be obligated to trend the performance of such components as required with components that meet the scope of OM-10.
4.10 Valve Test Acceptance Criteria i All valve test acceptance criteria (IST-TAC) will be developed in accordance with the provisions specified , in OM-10. The applicable acceptance criteria will be developed when the valve is known to be performing in a satisfactory manner. Where IST TAC other than that required by code is establishad for a given valve (e g., additional N.I.T. diagnostics), the documentation of that criteria will be at the discretion of the - licensee and not required to be part of the test record. Trending of valve IST-TAC will be performed by
/9 the licensee on a periodic basis. Leakage criteria for valves (other than those tested in accordance to V 10CFR50, Appendix J) will be determined based on leakage rates specified by the licensee or using the guidance specified in 4.2.2.3. Relief valve IST-TAC will be established per OM-1,1987.
Such IST-TAC should not be confused with the acceptance criteria specified in DBDs, DBD associated TAC Sheets, Technical Specifications, or any FSAR. Such acceptance criteria are the most limiting values and can not be exceeded. IST-TAC are set to verify operational readiness of the valves and to identify valve degradation before the 'most limiting' acceptance criteria is exceeded. IST-TAC are based upon stroke times measured when the valve is know to be in good working order and are controlled within the test procedures. Alternately, DBD-TAC are specific criteria associated with a valve's design basis. 4.10.1 Valve Stroke-Time Acceptance Criteria: The following cases present the options available for determining valve operability based on stroke s time: CASE 1 : The valve strokes within its acceptable stroke time. The valve is considered operable. CASE 2: The valve does not move at all on the first try or exceeds the LIMITING VALUE. OM-10 immediately refers to this valve as being inoperable. An engineering evaluation needs to be done to determine the cause of the valve failure and system operability. CNS ASME In-service Testing Program Rev. 00 Page 12 of 34 CNSSCOPE. DOC 12/14/95
4.10. . Valve Test Acceptance Criteria (continued) 4.10.1 Valve Stroke Time Acceptance Criteria': {
# , CASE 3 : The valve fails to meet the acceptance stroke time, but strokes in less than l
1 the LIMITING-VALUE. Per OM-10, the valve aball be immediately retested - ;
'~
to achieve an acceptable stroke time. Per the. Catawba valve testing j program 4 ; j' . j a. If the valve successfully strokes on the _ Retest, the valve is ; j considered operable. The cause of the initial deviation shall be .{ j analyzed and the results documented in the test procedure. A third i valve stroke may be performed to demonstrate consistent valve
- j. operabon j j b. If the valve does not fall within the acceptable range on the Retest, i then the valve is declared inoperable. An evaluabon must be !
l performed to determme the root cause of the failed test. The evaluation may determme that erther correchve maintenance must !
- be performed on the valve at the new stroke data is acceptable ;
j and new baselines must be established. Such results must be { j documented in the test procedure. !
- c. In the event the initial stroke and ' the Retest results are j i inconsistent, but the engineering evaluation shows the new stoke- :
- time is acceptable, a third test may be performed to verify l consistent behavior. Documentation of the third test wil; be optional ;
l
- if it shows Da deviation from the ' Retest".
I 4.10.2 Valve Stroke-Time Measurements and Methods: g ( j Valve stroke-times are measured with a s^wpw.i,i to the nearest second The stopwatch is started i when the valve is actuated and it is stopped when an indication light is received indicating that the
- - valve has cchi
- ^d its full stroke.
i ! 4.10.3 Limiting-Value Stroke-Time Acceptance Criteria: I Limiting-Values for stroke-times will be established in accordance with guidance given in Generic L Letter 89-04, Position 5. It is the position of the licensee that these values will be determined as follows (with the limitations of Tech. Specs. and Safety Analysis limits being the most limiting): Valve Tvon Limitina Value Calculaton ! EMO (> 10 secs.) 1.3R (to the nearest 0 or 5sec.) j EMO (s 10 secs.) 1.5R (to the nearest 0 or 5sec.) L POV (> 10 secs.) 2.0R (to the nearest 0 or 5sec.) POV(s 10 secs.) 2.25R (to the nearest 0 or 5sec.) l Note: Where 'R' represents the valve reference value at acceptable operation. i 4.10.4 Engineering Evaluations: (Discussion to be completed for CNS next revision)
- I i
d CNS ASME in-service Testing Prograrn
- l. Rev. 00 Page 13 of 34 ,
i CNSSCOPE. DOC 12/14/95. j l
4 1 5.0 PUMP PROGRAM V 5.1 in-Service Testing (IST) Program As required by 10CFR50.55a certain pumps that are classified in accordance of NRC Regulatory Guide 1.26 as ISI Class A, B, or C, which corresponds to ASME Class 1,2, or 3 respectively are included in the IST Program. The following defines the enteria for inclusion of equipment in the IST Program: ! Pumps in systems specifically required by Technical Specifications to be tested per a) ASME Section XI. b) All pumps that fall within the Duke ISI Class A, B, or C boundaries that are provided with an emergency power source and are also active in mitigating the consequences of the Design Basis Accidents (Design Basis Accidents are defined as those described
, in FSAR Chapter 15).
Currently Catawba Nuclear Station is under the requirements of the ASME Code and Standards, OM PART 6,1987 Edition, including OMb-1989 (which is OMa-1988 plus Errata Addenda to correct Table 3). This was the Code in effect 12 months prior to the anniversary date of the CNS 120-month update. 5.2 Pump Testing Program Exemptions and Position Statements Pumps tested under the jurisdiction of this program will be tested per code requirements of OM-6 at the : specified frequencies unless it has been determined to be impractical. The purpose of this section of the program document is to provide CNS positions on interpretations, guidance and other options regarding testing attematives. 5.2.1 Seebon 7.3 requires the signature of the person or persons responsible for conducting and analyzing the test. The dated initials of the person or persons responsible for conducting and analyzing the test may be used in place of a signature in the record of 4 the tests. Initials shall be used as signatures to meet the intent of the OM-6 as long as somewhere in the test procedure the initials are identified by a full signature. l 5.2.2 Developed head acceptance should be rounded to the nearest 0.5 psi, if possible. In most cases the suction gauges used will allow this type of accuracy. 5.2.3 Vibration acceptance should be truncated to 2 decimal places for operability determinations. The full four digit display number should still be recorded. 5.2.5 Pumps whose only safety function is predicated on plant shutdown and recovery from a fire per commitments made as a result of 10CFR50, Appendix R are not included in the IST Program. The licensee will test these in accordance with Appendix R requirements. 5.2.6 Pumps that are not provided with an emergency source of power will not be requirod to meet IST requirements. The licensee however, may elect to include these pumps in the IST program for testing purpose only. O CNS ASME In-service Testing Program Rev.00 Page 14 of 34 CNSSCOPE. DOC 12/14/95
I 5.2 Pump Testing Program Exemptions and Position Statements (continued) C/ 5.2.7 Pumps which can only be tested during plant operation will be tested within 1 week following plant startup to comply with section 5.4 guidance. If the testing schedule is not maintained during plant shutdowns, the affected pump (s) must be tested before entering an operational mode which requires the pump (s) to be operable. The licensee however, may elect to delay repairs and/or retest of pumps not required to be operable for plant startup or other operational modes. 5.3 Mini-flow and Full Flow Pump Testing (Discussion to be completed at a later date.) 5.4 Vibration Monitoring Pump vibrations monitored under the jurisdiction of this program will be performed per code requirements at the specified frequencies unless it has been determined to be impractical or a specific deviation from code is needed . This purpose of this section of the program document is to provide the site's positions concerning interpretations, guidance and other options of vibration monitoring and analysis. Specific positions to certain sections to follow are currently being developed by the In Service Testing Working Group Team (ISTWG) and will be submitted in future revisions. 5.4.1 Pump drivers. (Discussion to be completed at a later date.) 5.4.2 Smooth Running Pumps. (Discussion to be completed at a later date.) 5.4.6 Vibration points for pumps. (Discussion to be completed at a later date.) l Q 5.5 Testing required from Remote Locations (Not Applicable to Catawba Nuclear Station) 5.6 Post Maintenance and Modification Testing (Retest) (Reference Nuclear System Directive: 408 Post-Maintenance Testing sections 408.9 and 408.10) 1 5.7 Skid-Mounted Pumps I Until the scope of components for 10CFR50.55a, is expanded to include all safety-related pumps and valves, and until the OM codes and standards specifically address skid-mounted components, the testing of the ' major' component supported by skid-mounted equipment will be an acceptable means for venfying the operational readiness of the skid-mounted equipment sub-components and assemblies. The licensee j however, may opt to include certain components contained on these skids in the IST program for testing purposes. In such cases, the licensee will not be obligated to submit Relief Requests or Justification for Deferrals nor will it be obligated to trend the performance of such components as is required for components that meet the scope of OM-6. i 5.8 Pump Test Acceptance Criteria l l All pump test acceptance criteria (IST-TAC) will be developed in accordance with the provisions specified 4 in OM-6. The applicable acceptance criteria will be developed when the pump is known to be performing
~in a satisfactory manner. Where IST-TAC other than that required by code is established for a given pump (i.e., pump curves), the documentation of that criteria will be at the discretion of the licensee and not i required to be part of the test record. Trending of pump IST-TAC will be performed by the licensee on a periodic basis.
l l i I l 4 CNS ASME in-service Testing Program Rev. 00 Page 15 of 34 CNSSCOPE. DOC 12/14/95
J 5.8 Pump Test Acceptance Criteria (continued) Such 'IST-TAC'should not be confused with the acceptance criteria specified in DBDs, DBD associated TAC Sheets, Technical Specifications, or any FSAR. Such acceptance criteria are the most limiting values and can not be exceeded. IST-TAC are set to verify operational readiness of the pumps and to identify pump degradation before the 'most limiting
- acceptance criteria are exceeded. IST-TAC are based upon performance data measured when the pump is know to be in good working order and are l controlled within the test procedures. Altematively, DBD-TAC are specific criteria associated with a j pump's design basis. l 1 5.8.1 Pump Hydraulic Acceptance Criteria: (Discussion to be included in next revision) l l
l
}
4 l 1 I CNS ASME In-service Testing Program Rev. 00 Page 16 of 34 CNSSCOPE. DOC 12/14/95
..-.r..--
k i 6.0 Relief Requests
) : The purpose of a Relief Request is to exclude components from testing requirements of the Code that cannot be followed Therefore, if the testing on the component can not be performed due to plant configuration, plant safety, equipment limitabons, type, or hazards to personnel, relief from the code will be requested.
- _ Submitted relief requests wilt (1) give an altamative method that ensures an acceptable level of quality and 1 safety, (2) explain the a hardship with meeting the code requirement, (3) provide a schedule or altemative test frequency (or duration for interim Relief Request). Relief Request for components that are in the iST
; Program will be sent to the NRC for approval. Each Ten Year Interval, when the site testing program is being 0 upgraded to the new testing requirements, all relief requests will be reviewed and re-submitted to insure that
- their reasons for issuance are still valid. In cases where a " Specific Relief
- was previously submitted to the 4- NRC and approval granted, but the conditions and provisions do not change (i.e. no code change or modificaton to equipment or system) to eliminate the relief, the relief will not require re-evaluation for the next
- Ten Year interval. Relief Requests will not be written for any non-Code Class components that are included i in the IST Program.
1 l
! 6.1 Implementing Relief Requests:
i When a Relief Requests is submitted for those requirements which have been determined to i be clearly impracbcal, the licensee reserves the right to implement the proposed attemative , testing while the NRC is reviewing the Relief Request, providing the licensee has assured j the altemative does not compiemise the level of safety provided by the code testing l requirement. This position is referenced from NUREG-1482, secbon 2.5. 4 1 6.2 Interim Relief Requests:
- When a Relief Request is required on an interim basis, the licensee will submit the relief for i review, but as with section 6.1, may implement the relief while the NRC is reviewing the request. Updates to schedules or impacts to modification implementation of the component
- i. with interim relief will be communicated to the NRC as the program is updated. Interim
- Relief Requests shall be withdrawn when the licensee no longer requires them.
l j i } i 1 CNS ASME In-service Testing Program Rev.00 ' Page 17 of 34 CNSSCOPE. DOC 12/14/95
l l t 7.0 Justifications for Deferrals: O V Justification for Deferrals (JFDs) will be written when a component can not be tested at the specified frequency. This could be due to an impracticality of testing the component at power or due to plant safety concems introduced by the testing configuration. The basis for determining the impracticality of testing at . i power and expanding the component's testing frequency to a Cold Shutdown or Refueling Outage frequency is documented in the Justification for Deferral. In-Service Testing to be performed at Cold Shutdown shall: a) be performed during each cold shutdown when the planned length is of sufficient duration to establish the necessary test conditions and to perfcnn the test, and b) be performed as to not impact the timely completion of the shutdown related activities and i subsequent retum to operation. For outages when the planned length is not of sufficient - duration to complete all tests, testing will start within 48 hours of reaching cold shutdown
- conditions. This is supported by the position stated in OM-10, secten 4.3.2.2, OMa-1988 Addenda.
c) be performed at the next available cold shutdown consistent with the above criteria if an 4 opportunity to test the valve is not available (Completion of the IST is not a prerequisite to return to operation), Any testing required to be performed during a refueling outage shall be completed prior to plant operation.
- Components tested during start-up will not delay start-up if the site Technical Specifications allow start-up j with the component out of service or inoperable. Retest and corrective actions shall be performed at the A first available opportunity.
7.1 Testing Deferral Justifications: l 7.1.1
Purpose:
The purpose of the testing Justification for Deferral form is to ) l document the reason that a pump or valve can only be tested at J cold shutdown or at refueling outage
+
! Valid reasons could be plant configuration for testing which would jeopardize the safety of ) l plant operation, access to the component which would be against ALARA, access to the l component due to the environmental conditions endangering personnel safety, or that plant ! l l configuration for testing would require the plant to be in a mode not suitable for power ! produchon Removing one train for testing or entering a Limiting Condition of Operation (LCO) is not sufficient basis for not performing the required tests, unless the testing renders systems inoperable for extended periods of time. It is not the intent of IST to cause unwarranted plant shutdowns or to unnecessarily challenge other safety systems. Other , i factors such as the effect on plant safety and the difficulty of the test should be considered.
! As =+M earlier. taating should not interfere with oower orodur+itsn.
No.te: The Justification of Deferral Form is found in Enclosure 9.6/ i-3 a i CNS ASME In-service Testing Program Rev.00 Page 18 of 34 CNSSCOPE. DOC - 12/14/95
I l l 8.0 APPENDICES 4 O h I . Appendix A: IST PROGRAM Responsibilitise -l 1 i 1.0 Site IST Engineer: '
- The IST Engineer position will be filled by a qualified individual knowledgeable of plant system operatian. He/she ensures the site is in compliance by its perfonnance testing and j 4
trending methods. The IST Engineer will accomplish this by maintaining consistency among l
' the System Engineers and overall program management. !
i The IST Engineer may publish an overall summary (as an annual summary), on the current status of the site performance monitoring of the valves and pumps tested under the requirements of the IST or 10CFR50, Appendix B program.
- The IST Engineer will be responsible for notifying Regulatory Compliance of any changes to ,
the Valve and Pump Testing Program described in this document, including changes to the l data sheet information The IST Engineer will be responsible for updating and maintaining the IST Database. The IST Engineer will be responsible for coordinating and implementing the program update ,! and renewal per 10CFR50 every 10 years. l
- 2.0 GO IST Coordinator
- ;
! The General Office (GO) IST Coordinator will be an individual responsible for overall corporate IST program management. He/she ensures Duke Power's corporate strategies for j the IST Program align with industry and regulatory standards. This individual is 9 knowledgeable of each site's IST programs including program administration and will be l l responsible for ensuring each site is in compliance with the applicable ASME Codes and IST ' l ! guidelines (OM-6, OM-10, GL 89-04, NUREG-1482 etc.). l The GO IST Coordinator will be the technical consultant on any Code-related issues that 3
- require interpretation or involve Operability determinations (at the discretion of the IST i Engineer and site management). The GO IST Coordinator will provide support for intemal ;
j and extemallST program audits. i j The GO IST Coordinator will be the Single Point of Contact on any issues that involve site- l site interaction. The GO IST Coordinator will be responsible for ensuring consistency where l J practical.
)I l
The GO IST Coordinator will represent Duke Power's interest for Code development. i The GO IST Coordinator will be responsible for assisting with review and updating the IST program per 10CFR50 each 10 year interval. He/she will also assist the sites in preparing, 2 submitting, and reviewing interim revisions to the IST program. Also, the IST Coordinator will
; assist the sita IST Engineer in developing position statements, Relief Requests, and
! Justification for Deferrals. He/she will also perform periodic reviews of site Relief Requests
, and/or Justificaten for Deferrals for consistency and compliance.
%]
CNS ASME In-service Testing Program i'- Rev. 00 Page 19 of 34
; CNSSCOPE. DOC 12/14/95
_- ~ b 4 Appendix A: IST PROGRAM Responsibilities (Continued)
\
2.0 GO IST Coordinator (continued): The GO IST Coordinator will see that progress addressing technical issues will be made by the IST Working Group (ISTWG). This includes defining appropriate tasks, tracking action - , 4 items, conducting periodic meetings, interface with the appropriate BEST contacts, and I maintaining overall group focus, i 3.0 Mechanical Systems Engineerina (MSE) " MSE (site) is responsible for the following: e ensuring the accuracy of IST dataset information, e defining test acceptance criteria (TAC), e ensuring code testing requirements are met,
- e documenting reasons for scope or code deviation, i
e providing tech. assistance for developing test procedures, e complete valve and pump data sheets for program revisions i j Each Mechanical System Engineer is responsible for the components within their systems which are in the program. If the status of a component changes, the MSE is responsible for
- initiating the required changes to the program (see Appendix C).
4.0 Cml/ Electrical / Rotating Faninment and Nerlaar Engineerina (CERN) D CERN is responsible for the following: e notifying the IST Engineer of maintenance that could affect the baseline data for any IST component,
~
e overall administration of the relief valve testing program (OM-10).
- administrating the check valve sample disassembly program, (
- e provide input when evaluating specific compenent issues (why failed test, baseline J changed, etc. ) !
5.0 Ooerations Performance Test Grouo (OTG) ) This group is responsible for the following: 6 e data in procedure and IST database, e performing tests, e accurately recording and notifying MSE of any testing problems, e initiating a PIP when a test is failed or a problem is encountered, ; e documenting test discrepancies on the procedure. 6.0 Ooerations Procedure Grouc This group is responsible for the following: i I e updating and maintaining all IST procedures, e verifying all technical changes with the IST Engineer. O
- CNS ASME in-service Testing Program Rev. 00 Page 20 of 34 CNSSCOPE. DOC 12/14/95 l
7 .,
} ..
i Appendix B: 10CFR50, Appendix B Program (Supplemental Testing Program) 1 O
\ CJ '
[+ The scope of the Catswba hump and valve testing program includes: l (1) all components that are active in mitigating the consequences of Design and non-j Design Basis Events, are required for cold shutdown,' (2) provide a containment isolabon function, I (3) or are designated by station Technical Spedf.c tions to be included in testing programs.
- This scope is further divided into IST testing and 10CFR50, Appendix B testing. (Reference
- d. Duke Power Company's Oconee Nuclear Station's 11/1/90 Generic Letter 89-04 response -
l M. S. Tuckman to NRC) 1 Selected cciTipenents tested under guidelines of 10CFR50, Appendix B porbon of the f Catawba Pump and Valve testing program provide a function important to the safety of l nuclear power plant operation, but are not explicitly under the scope of ASME OM Codes , ' and Standards or considered beyond the scope of 10CFR50.55a. Specifically, the > 10CFR50, Appendix B psogramincludes (1) pumps and valves not included in the IST program which are active in certain non - Design Basis Events, (2) are cold shutdown valves not associated with a FSAR Chapter 15 event, , ) (3) are significant to plant safety, (4) or are of economic importance. 1 [ The CNS 10CFR50, Appendix B Program will be administered using the ASME IST Code as guidance for testing and trending. The acceptance criteria and testing intervals used to test . Appendix B cciTvenents should be specified by the IST Engineer. Relief Requests and + Justification for Deferrais will not be submitted for Appendix B components. If the requirements of the ASME Code cannot be followed for components in the Appendix B
- program, deviations from Code ' guidelines' will be documented in the section j " SUPPLEMENTAL PROGRAM POSITIONS" 4
The 10CFR50, Appendix B coi6ponents will be tested using approved Duke Power "A" l procedures and requirements of 10CFR50, Appendix B. Deviations from standard test procedures, will be allowed only if substantiated in writing per the methods outlined in the
! - Attachments to this document.
I APPENDIX B. SUPPLEMENTAL PROGRAM POSITIONS. B.1 Per Catawba's GL.89-04 response,10 CFR 50, Appendix B manual valves are only stroked at a l refueling frequency. I: i CNS ASME In-service Testing Program Rev.00 . Page 21 of 34 E CNSSCOPE. DOC 12/14/95 '
.y.
Appendix C: Notification of Program changes The System Engineer shall initiate program changes as changes are made to the respectue system, DBDs, or active / passive valve calculations. Notification of extemal customers (e.g. Regulatory Compance Group) of such changes to the program will occur by issuing the appropriate administrative mechanism (ie. PIP, Minor Modification Request, etc.). I 1 I l l i l l l l l l l
)
1 l l l r i i i n 4 t i CNS ASME In-service Testing Program f Rev. 00 Page 22 of 34 CNSSCOPE. DOC 12/14/95
- - . _ .. . .. .. - . . . . - . - . . ~ . - . . . . . . . - . - - . . - . . - . - . . - . . . _ - . . - . - . - . . .
i t-9.0 ENCLOSURES, i i Enclosure 9.1 1-i (RESERVED FOR NEXT PROGRAM DOCUMENT REVISION) d T 1 i i 1 i i 4 i' i i i i i 1 i i' 4 1 1 '.i l i k i 1 4 i 4 1 l i l i 1 i 1 i i e i s
]
i J < CNS ASME in-service Testing Program Rev. 00 Page 23 of 34 i CNSSCOPE. DOC 12/14/95
Enclosure 9.2 To ensure Code compliance for the CNS Pump and Valve Testing Program, the IST Engineer should be notified of any of the following changes: e changing the active / passive status of a component, e cha,1ging the leakage requirements of the component, e changing the piping classification of the component (Duke Class and ISI Class), e something changes with how the component may be tested, e a commitment is made or changed for testing or operation of a component, e taking credit for a new function, flow path, etc., O n U CNS ASME In-service Testing Program l Rev,00 Page 24 of 34 CNSSCOPE. DOC 12/14/95
Enclosure 9.3 [ Valve Data Sheet
, Revision Addition Deletion Reason for change Valve Number - Description Valve Type. BA BF CK Di .EX GB GT {
PG PR RV SC ST SV VB Valve Size Actuator Type AO HO MA ML MO MR PA SA SO Flow Diagram Coordinate System Engineer PROFS ID Containmentisolation Valve Yes No Generic Letter 8910 Valve Yes No a Active Valys Yes No ESF Valve Yes No , Auxiliary Safe Guard Valve Yes No Skid Mounted Valve Yes No Vent / Drain Yes No i Valve Category A B C D (See OM-10 section 1.4) ASME Class A B C N (non code class) Required Accident Position Open Closed Throttled i ! Cold Shutdown Position Open Closed Throttled 4 Alternate Feedwater Path Yes No l DBD Time OPEN DBD Time CLOSED ! TS Time OPEN TS Time CLOSED i-FSAR Ume OPEN FSAR T me CLOSED Valve Test Type FS PS ST LJ LT l Test Direction OC CO BOTH Test Frequency Q CSD RF i Test Procedure 1
- CNS ASME In-service Testing Program Rev,00 Page 25 of 34 CNSSCOPE. DOC 12/14/95
i 1-Enclosure 9.4 O . Pump Data Sheet Pump (s): . Reviolon Addition Deletion ) Reason for Change Pump information 181 Class A B C Duke Class A B C D F G Pump Manufacturer - Pump Type - 1 I Pump BEP (Design Pt.) - gpm psi Driver Manufacturer - ! Driver Size - ! OFD - Coor. 5 ES Actuation Channels 1 2 3 4 5 6 Procedure No(s).: - Accident Pump Flow - Delta P Required - Full Flow Requirement - 4 TAC Sheets - Procedure No(s).: - Test frequency Q CSD RF O CNS ASME In-service Testing Program Rev. 00
- Page 26 of 34 CNSSCOPE. DOC 12/14/95
1 b
, Enclosure 9.5 i
Catawba Units 1 and 2 4 l J I Generic Relief Request I i 4. i item Number. Component Number (s): j Flow Diagram (s): I - Function (s): 1 j ISI Class / Duke Class: I' Code Category: l Test Requirement (s): 4 O Basis for Relief: l a i Code Altemative: l. i i i i l l 1 4 CNS ASME In-service Testing Program - Rev.00 Page 27 of 34 CNSSCOPE. DOC 12/14/95 i
i 1 ' m Enclosure 9.6 Catawba Units 1 and 2 .t I-l Justification for Deferral Item Number: ) . Component Number (s): Flow Diagram (s): l
- Code Category 4
ASME Class: l Function (s): Test Requirement l Basis for Deferral: t t f i
- Test Attemative & Frequency; i
a l I 5 i l
!O l 1 l i
CNS ASME In-service Testing Program I Rev. 00 Page 28 of 34 CNSSCOPE. DOC 12/14/95 l i_______________________._._ _ _ . . . . _ . _ .._
- . - - =- -
f 4 Enclosure 9.7 Catawba Units 1 and 2 ( . j j Specific Relief Request i I ! Item Number. Component Number (s): j Fkm Diagram (s): Function: ASME Class': i j Code Category: Test Requirement: i . 1 l I i ! Basis for Relief: i ' l i i
- Altemate Testing
1 l i J l 1 d t- ) CNS ASME In-service Testing Program
- Rev.00 Page 29 of 34 l CNSSCOPE. DOC 12/14/95
d--h.= 4 4 4 r 4 - 5 ... - b-'gh... J s_-- m' . - ..i.ii4 a+ r_ & 4__ ._.. Enclosure 9.8 V System Piping Classification Correlation i Seismic Normally Duke (1) NRC ANSI Pressure Contains < System Piping Safety Quality Duke QA Safety Boundary Seismic Radioactive Claanification Related Groun Condition Clana Code Des Critaria (6) Intsprity Category Material A YES A 1 1 Class 1, ASME Sect. til YES SC-1 YES-B YES B 1 2 Class 2, ASME Sect. til YES SC-1 YES C YES C 1 3 Class 3. ASME Sect. til YES SC-1 YES i D NO - 4 NNS(2) Class 2, ASME Sect.111 YES SC-ll(7) NO E NO- D(3) 2(4) NNS(2) ANSI B31,1.0 NO N/A YES F. YES B,C 1 2,3 ANSI B31.1.0 YES SC-1 NO , G NO -
-(4) - ANSI B31.1.0 NO N/A NO H NO -
-(4) - Duke Power Spec. NO N/A NO H (HVAC) YES -
-(6) - Duke Power Spec. YES SC 1 NO j NOTES:
(1) Safety Related as used herein is in accordance with 10CFR50 Appendix A General Design Cnteria for O Nuclear Power Plants and is applicable to function only; l.e., structures, systems, and components required to function such that the faciltty can be operated without undue risk to the health and safety of the public are safety related. 1 (2) NNS = Non-Nuclear Safety i (3) Class E piping is equivalent to NRC Quality Group D; i.e., the system is designed to normally carry a radioactive fluid; however, is considered NNS as a component failure would not result in a calculated d potential exposure in excess of the limits established by 10 CFR PART 20. (4) Class E, G, and H piping systems may also be assigned QA Condition 3 and/or 4 to denote additional requirements for fire protection of safety related components and/ or seismic structural integnty (except pressure boundary) to preclude adverse interactions with safety related structures, systems and j components, respectively; refer to Duke Nuclear Guide 1.29. j . (5) Code and Standards Applicability: Duke Power Company establishes an " effective code date"in accordance = with 10CFR50, par. 50.55a for Catawba Nuclear Station. Due to the numerous code and standards j references applicable to each station, no attempt is made to specifically identify these references as they are amended, superseded, or substituted. Duke reviews and complies with all or portions of the latest versions of the above Codes and Standards unless matenals and/ or design commitments have progressed to a stage that it is not practical to make a change. When only portions of addenda to Codes and Standards are utilized, the appropriate engineering review of the entire agenda assures that the overall intent of the Code Standard is still maintained. (6) HVAC Duct Systems may be constructed of either sheet metal or piping materials depending upon the design function and requirements. Non-Safety Related HVAC may be assigned QA Condition 4, SC-11 4 Support Restraints to preclude adverse interactions with safety related structures, systems, and a components. Refer to Duke Nuclear Guide 1.29. O (7) Class D for piping systems is used when pressure boundary protection is required. Seismic Category ll hangers may be use on Class E, G, or H piping systems when pressure boundary integrity is not required. See Duke Guide 1.29. CNS ASME in-service Testing Program
. Rev.00 Page 30 of 34
- CNSSCOPE. DOC 12/14/95
t Enclosure 9.9 ! O Summary of.lST Program 10 yr. Submittal Changes
- U
\
I
- 1. Reviewed all components from the 1st interval Program Submittal to verify inclusion into the 2nd 10 year interval Program Submittal based on scope of OM4 (pumps), OM-10 (valves), and OM-1(relief valves).
i'
- 2. Updated valve data-sheets utilizing new DUKE format (as agreed to by the ISTWG) and incorporating the abbreviations from NUREG-1482.
I 3. Created a PROGRAM DOCUMENT for the CNS IST program which does the following: i i o defines key terms and definitions used in the IST program. i o defines the valve testing program including exemptions and position statements. e defines the pump testing program including exemptions and position statements. l 4 o defines implementation and interim use of relief requests. l c defines use of justifications for deferrals. o defines IST program controls and revisions processes. , o provides discussion for key IST position statements: j - . Thermal Relief Check Valves
. VP Valve stroke time testing exemption
. VY Valve stroke time testing exemption.
l
- 4. Deleted all valve Relief Requests.
l 5. Added Pump Relief Request CN-SRP-CA-01. ! o CA Pump flow gauge instrumentation greater than three (3) times the reference range of 3 expected flow measurement.
- 6. Converted previously approved Cold Shutdown Relief Requests to Cold Shutdown Justifications for Deferrals.
f
- 7. Changed several valves from " active" to " passive" based on code interpretation reference changes to VP and VY systems. This will allow deletion of test requirement to stroke time test VP and VY Containment isolation valves.
G. Added valves 1(2) KC-280 from the KC SITA audit. Design basis for va!ves meet the scope of OM-
- 10. -
i
, 9. - Incorporated CNDS-0113 check and relief valves into the IST program as reemmended by the
\ responsible System Engineer. The following valves were added to the avgram J I
CAS ASM2 : ocervice Testing Program
ev,00 Page 31 of 34 C6C *COPEDSM 12/14/95
Enclosure 9.9 ; i Summary of IST Program 10 Year Submittal Changes (Continued) j U a' CHECK VALVES RECOMMENDED POR ADDITION TO MA/ PROGRAM l g '1CF 31 STEAM GENERATOR 1A CONT ISOL INLET CHECK ; l 1CF 40 STEAM GENERATOR 1B CONT ISOL INLET CHECK ; 1CF-49 STEAM GENERATOR 1C CONT ISOL INLET CHECK 1 1CF-58 STEAM GENERAT OR 1D CONT ISOL INLET CHECK 1CF 169 - STEAM GENERATOR 1D FEEDWATER TO AUX. FEEDWATER NOZZLE CHECK 1 1FD-29 - DIESEL GENERATOR ENGINE DRIVEN FUEL OIL PUMP 1 A DISCHARGE CHECK l '1FD49 .. DIESEL GENERATOR ENGINE DRIVEN FUEL Oft PUMP 18 DISCHARGE CHECK' 1KC-344 - REACTOR COOLANT PUMP 1C THERMAL BARRIER INLET CHECK p 1KC-363 - REACTOR COOLANT PUMP 1 B THERMAL BARRIER INLET CHECK 1KC-393 REACTOR COOLANT PUMP 1A THERMAL BARRIER INLET CHECK ,- 1KC-412 REACTOR COOLANT PUMP 10 THERMAL BARRIER INLET CHECK ; i 1LD 17 LUBE OIL STRAINER 1A1 CHECK . ! 1LD-18 ' LUBE OIL STRAINER 1A2 CHECK . l 1LD-47 LUBE OIL STRAlNER 181 CHECK ' j 1LD-48 LUBE Oil STRAINER 1B2 CHECK
- 1LD-71 LUBE OIL STRAINER 1A1 CHECK j 1LD-72 LUBE OIL STRAINER 1A2 CHECK j 1LD-78 LUBE OIL STRAINER 181 CHECK j 1LD-79 LUBE OIL STRAINER 182 CHECK
! 1VG-133 DIESEL GENERATOR STARTING AIR TANK 281 SUPPLY to ENGINE CNTRL PANEL 2B
, 1VG-134 DIESEL GENERATOR STARTING AIR TANK 282 SUPPLY to ENGINE CNTRL PANEL 2B 1VG-135 DIESEL GENERATOR STARTING AIR TANK 2A1 SUPPLY to ENGINE CNTRL PANEL 2A I p 1VG-136 . DIESEL GENERATOR STARTING tlR TANK 2A2 SUPPLY to ENGINE CNTRL PANEL 2A 1 l 1WL430 TURBINE DRIVEN CA PUMP 1 SUMP 2A DISCHARGE CHECK j 1WL-832 TURDINE DRIVEN CA SUMP PUMP CHECK VALVE l l 2CF-31 STEAM GENERATOR 2A CONT ISOL INLET CHECK i 2CF-40 STEAM GENERATOR 2B CONT ISOL INLET CHECK l 2CF-49 STEAM GENERATOR 2C CONT ISOL INLET CHECK l 2CF-58 STEAM GENERATOR 2D CONT ISOL INLET CHECK l l . 2CF 16J ' STEAM GENERATOR 20 FEEDWATER TO AUX. FEEDWATER NOZZLE CHECK l l 2FD-29 DIESEL GENERATOR ENGINE DRIVEN FUEL OIL PUMP 2A DISCHARGE CHECK l 2FD49 DIESEL GENERATOR ENGINE DRIVEN FUEL OIL PUMP 28 DISCHARGE CHECK ]
- j. 2KC-M4 REACTOR COOLANT PUMP 2C THERMAL BARRIER INLET CHECK I j 2KC-363 REACTOR COOLANT PUMP 28 THERMAL BARRIER INLET CHECK )
2KC-393 REACTOR COOLANT PUMP 2A THERMAL BARRIER INLET CHECK 2KC-412 REACTOR COOLANT PUMP 2D THERMAL BARRIER INLET CHECK . 2LD-17 LUBE OIL STRAINER 2A1 CHECK
! 2LD-18 LUBE OIL STRAINER 2A2 CHECK j 4 2LD-47 LUBE OIL STRAINER 2B1 CHECK l
) 2LD-48 LUBE OIL STRAINER 2B2 CHECK 2LD-71 LUBE OIL STRAINER 2A1 CHECK } 2LD-72 LUBE OIL STRAINER 2A2 CHECK
)
4 2LD-78 LUBE OIL STRAINER 2B1 CHECK 1 2LD LUBE OIL STRAINER 282 CHECK
]
j 2VG 133 . DIESEL GENERATOR STARTING AIR TANK 2B1 SUPPLY to ENGINE CNTRL PANEL 28 2VG-134 DIESEL GENERATOR STARTING AIR TANK 2B2 SUPPLY to ENGINE CNTRL PANEL 2B l 4 2VG-135 DIESEL GENERATOR STARTING AIR TANK 2A1 SUPPLY to ENGINE CNTRL PANEL 2A l 2VG-136 DIESEL GENERATOR STARTING AIR TANK 2A2 SU' PLY to ENGINE CNTRL PANEL 2A !
. 2WL430 TURBINE DRIVEN CA PUMP 1 SUMP 2A DISCHARGE CHECK 2WL432 TURBINE DRIVEN CA SUMP PUMP CHECK VALVE 4
CNS ASME in-service Testing Program Rev 00 Page 32 of 34 l 4 CNSSCOPE. DOC 12/14/95 p
c Enclosura 9.9 Summary ofIST Program 10 Year Submittal Changes (Continued) RELIEF VALVES RECOMMENDED FOR ADDITION TO IWV PROGRAM 1FD-34 D/G ENG 1A FUEL OIL RN 1FD-74 D/G ENG 1B FUEL OIL RN 1LD-2 1A ENGINE DRIVEN LUBE OIL PUMP SUCT REUEF 1LD-32 1B ENGINE DRIVEN LUBE OIL PUMP SUCT RELIEF 1ND-3 ND PUMP 1A SUCT FROM NC LOOP B HDR RELIEF 1ND-31 ND TRAIN 1 A COLD LEG INJECTION RETURN SAFETY RELIEF 1ND-35 ND HOT LEG INJECTION RETURN SAFETY RELIEF 1ND-38 ND PUMP 1B SUCT FROM NC LOOP C HDR RELIEF 1ND44 ND TRAIN 18 COLD LEG INJECTION RETURN SAFETY. RELIEF 1NI-102 NI PUMPS SUCT HDR REUEF 1NI-119 NI PUMP 1A DISCH HDR RELIEF 1NI-151 Ni PUMP 1B DISCH HDR RELIEF 1NI161 NI TO C-LEGS REUEF INM-69 N1 ACCUM SAMPLE RELIEF 1NV-14 LETON ORIFICE HDR RELIEF 1NV-87 NC PUMPS SEAL RETURN HDR INSIDE RELIEF 1NV 205 SEAL WATER RETURN RELIEF 1NV-222 SEAL WATER RTN RN 1NV-223 VCT REUEF TO RHT 1NV-273 NV PUMPS A&B SUCT HOR RELIEF 1NW-247 RELIEF VALVE 1NW-248 RELIEF VALVE p 1NW-249 RELIEF VALVE l 1RN-854 RN PUMP 1A DISCH. VACUUM BREAKER I 1RN-855 RN PUMP 18 DISCH. VACUUM BREAKER 2FD-34 D/G ENG 1A FUEL OIL RN 2FD 74 D/G ENG 18 FUEL OIL RN 2LD-2 2A ENGINE DRIVEN LUBE OIL PUMP SUCT REUEF 2LD-31 2B ENGINE DRIVEN LUBE OIL PUMP SUCT RELIEF l 2ND-3 ND PUMP 2A SUCT FROM NC LOOP B HDR RELIEF ! 2ND-at St ND TRAIN 2A COLD LEG INJECTION RETURN SAFETY RELIEF 2ND-35 ND HOT LEG INJECTION RETURN SAFETY RELIEF l 2ND-38 ND PUMP 2B SUCT FROM NC LOOP C HDR RELIEF 2ND-64 ND TRAIN 2B COLD LEG INJECTION RETURN SAFETY REllEF l 2Ni-102 NI PUMPS SUCT HDR RELIEF 2NI-129 NI PUMP 2A DISCH HDR RELIEF 2NI-151 Ni PUMP 2B DISCH HDR RELIEF 2NI-161 NI TO C-LEGS RELIEF 2NM-69 NI ACCUM SAMPLE RELIEF ) 2NV-14 LETDN ORIFICE HDR RELIEF l 2NV-87 NC PUMPS SEAL RETURN HDR INSIDE RELIEF 2NV-205 SEAL WATER RFTURN REUEF j 2NV-222 SEAL WATER RTN RN { 2NV-223 VCT RELIEF TO RHT 2NV 273 NV PUMPS A&B SUCT HDR RELIEF 2NW-247 RELIEF VALVE 2NW-248 RELIEF VALVE 4 i 2NW-249 RELIEF VALVE 2RN-854 RN PUMP 2A DISCH. VACUUM BREAKER 2RN-855 RN PUMP 2B DISCH. VACUUM BREAKER l CNS ASME In-service Testing Program Rev. 00 Page 33 of 34 CNSSCOPE. DOC 12/14/95
Enclosure 9.9
, (Q v j Summary of IST Program 10 Year Submittal Changes (Continued)
- 10. Added valves 1,2lASV5400 and 1,2iASV5410 to the IST (IWV) program. Design basis for valves meet the scope of OM 10.
- 11. Removed valves 1,2NI-125 and 1,2NI-129 from the IST (IWV) program. Design basis for valves do not meet the scope of OM-10.
t
- 12. Added/ modified the following JFDs:
o CN-NV defers stroke timing NV-10A,11 A,13A to cold shutdown. 4 o CN-CA-03 states reverse flow test for CA-8,10,12 will be complied with via sample disassembly.
= CN-Ni added valves 1,2N1134 to deferral justification.
- 13. Deleted JFD CN-IA-02: Justification for not performing remote indication testing was not valid.
- 14. Deleted JFD CN-RN-01: justification for not performing stroke time tests on quarterly interval is no Q
v longer valid due to modification to RN System. I o Affects valves RN-49A, RN-508, RN-51 A, RN-52B. <
- 15. Removed valves RN36A,378,67A, 698, 287A,3478,429A and 4328 from program. Valves do not meet the scope of OM-10 after modifications.
- 16. Added valves KCC37A and KCC40B to program after KC SITA. Valves meet the scope of OM-10. l i \
l I l , l i CNS ASME In-service Testing Program Rev. 00 Page 34 of 34 CNSSCOPE. DOC 12/14/95
4 4 Table of Abbreviations Parameter ' Abbreviation - Description - Actuator Type MO Motor operated i SO Solenoid operated AO Air operated HO Hydraulic operated SA Selfactuated MA Manual PA Pilot Actuated ; Safety Position (s) O Open C Closed O/C Both open and closed i T Throttled Test Performed FS Full-stroke exercise to safety position (s) PS Partial-stroke exercise LT Leak-rate test to Section XI requirements - LJ Leak-rate test to Appendix J requirements ST Measure the full stroke time of the valve l FT Observe the fail-safe operation of the valve PI Verify the valve's remote position indication RV Safety and relief valve test 1 EX Explosive valve test Test Frequency Q Test performed once quarterly CS Test performed at cold shutdown RF Test performed each reactor refueling outage 1 2Y Test performed every two years
- RV Test relief valve at OM 1 schedule ILRT Test containment isolation valve at ILRT schedule i SD Disassemble, inspect, and manually exercise one j
[ ' valve from specified group each reactor refueling outage
- Test Alternatives RF Perform during refueling (Mode 6)
Z Exercise valve (partial stroke) for operability d every 3 months during power operation and l
- exercise valve (full stroke) for operability during cold shutdown (mode 5).
i ! I D< V SECTION 2.0 Page 1 of 2
s i - l Numbering Sequence for Relief Request and Justification For Deferral Examples: , j RELIEF REQUEST JUSTIFICATION FOR DEFERRAL J l CN- SRP- VG- 1 CN- VG- 1 d SEQUENCE SEQUENCE i SYSTEM SYSTEM a d t STATION (SPECIFICor QENERIC) , BELIEF for RUMP orYALVE) I STATION O 4 i e 4 . SECTION 2.0 Page 2 of 2
l l' J f f i I
- i CATAWBA NUCLEAR STATION
( Unit 1 I i i !O
- ASME Inservice Testing Program i
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UNIT 1 - CATAWBA NUCLEAR STATION Pump inservice Testing Program Code best DtNorontist Flow ' Daeceiptsen Onee Pump Type Flow Dimereni Speed. Prenews Frenewe Vihregion . Rose hellef Hoguest Renneae - how Pump g). Mienber 1CAPUOOO1 Motor Driven 3 Centrifugal CN-1592-1.0 NR Q Q Q Q CN-SRP-CA-01 NONE ~23 Auxiliary Feedwater Pump 1 A 1CAPUOOO2 Motor Driven 3 Centrifugal CN-1592-1.0 NR Q Q Q Q- CN-SetP-CA-01 NONE 23 Auxiliary Feedwater Pump 18 1CAPUOOO3 Turtune Driven 3 Centrifugal CN-1592-1.0 Q Q Q Q- Q NONE. 23 Auxiliary Foodwater l Pump #1 1KCPUOOO1 Component Cooling 3 Centrifugal CN-1573-1.0 NR Q Q Q Q' NONE- 23 Water Pump 1 A1 ; l 11".CPUOOO2 Component Cooling 3 Centrifugal CN-1573-1.0 NR Q Q Q Q NONE 23 Water Pump 1 A2 , i 1KCPUOOO3 Component Cooling 3 Centrifugel CN-1573-1.0 NR Q Q Q Q NONE 23 Water Pump 1B1 1KCPUOOO4 Ccmponent Cooling 3 Centrifugal CN-1573-1.0 NR Q Q Q Q NONE 23 Water Pump 1B1 1NDPUOOO1 Residual Heat 2 Vertical Line CN-1561-1.0 NR O Q Q Q NONE 23 Removal Pump 1 A Shaft Centrifugal 1NDPUOOO2 Residual Heat 2 Vertical Line CN-1561-1.1 NR Q Q Q Q NONE 23 Removal Pump 1B Shaft Centrifugal Rev.23 SECTION 3.1 06/29/96 1 OF 2 ?
() p . ! U h t UNIT 1 - CATAWBA NUCLEAR STATION ! Pump Inservice Testing Program l c - no. Pump Type Flow Dimerem Spee. Prosesse Preesimo Vibroeien Rees Resef Regumet Romerke Rev Pump ID. mentier N C3ese Safety injection 2 Centrifugal CN-1562-1.2 NR Q Q Q Q NONE 23 l-1NIPUOOO9 Pump 1 A l 1NIPUOO10 Safety injection 2 Centrifugel CN-1562-1.2 NR Q Q Q Q NONE 23 Pump 1B 1NSPUOOO1 Containment Spray 2 Vertical Line CN-1563-1.0 NR .Q Q Q Q NONE 23 Pump 1 A Shaft Centrifugal 1NSPUOOO2 Containment Sprey 2 Vertical Lir e CN-1563-1.0 NR Q Q Q Q NONE 23 Pump 1B Shaft Centrifugal 1NVPUOO15 Centrifugel Charging 2 Centrifugal CN-1554-1.7 NR Q Q Q Q NONE 23 Pump 1 A INVPUOOl6 Centrifugel Charging 2 Centrifugal CN-1554-1.7 NR Q Q Q Q NONE 23 Pump 1B 1RNPUOOO2 Nuclear Service 3 Vertical Lhe CN-1574-1.0 NR Q Q Q Q NONE 23 Water Pump 1 A Shaft Centrifugal 1RNPOOOO4 Nuclear Service 3 Vertical Line CN-1574-1.2 NR Q Q Q Q. NONE 23 Water Pump 1B Shaft Centrifugal 1YCPUOOO1 Control Area Chilled 3 Centrifugel CN-1578-2.0 NR O O Q Q NONE 23 Water Pump Train A 1YCPUOOO2 Control Area Chilled 3 Centrifugal CN-1578-2.0 NR Q Q Q Q NONE 23 Water Pump Train B Rev.23 SECTION 3.1 06/29/96 2OF2
O O n
.v Unit 1 - Catawba Nuclear Station Inservice Testing Program now now AsuE vavt Act Act dosT dos T JustaroR Test vavE muusER OtAGAM COOR CLASS CATGRY PAS VMVE TYPE TYPE MOJ = No.2 REup MEQST DU5mR REu. MS RT5WAnVES REV -
CONTROL AREA CHILLED WATER SYSTEM (YC) 1YC065 CN-1578-2.0 C05 3 C ACT Check SA FSC-Q 23 1YC077A ' CN-1578-2.0 D12 3' B ACT Gate MO ST-Q PI 23 1YC108 CN-1578-2.2 C05 3 C ACT Check SA FSC-Q 23-1YC121B CN-1578-2.2 D12 3 B ACT Gate MO ST-Q Pt 23: NUCLEAR SERVICE WATER (RN) 1RN001A CN-1574-1.0 J07 3 B ACT Butterity MO . ST-Q Pi 23 1RN002B CN-1574-1.0 J07 3 B ACT Butterfly MO ST-Q Pt 23 1RN003A CN-1574-1.2 J11 3 B ACT Butterfly MO ST-Q Pt 23 1RN004B CN-1574-1.2 J05 3 B ACT Butterfly MO ST-Q Pl. 23 1RN005A - CN-1574-1.0 K05 3 B ACT Butterity MO ST-Q PI -23 1RN006B CN-1574-1.0 K04 3 B ACT Butter 1Iy MO ST-Q Pt 23 1RN0538 CN-1574-1.1 D09 3 B ACT Butterfly. MO ST-Q Pt 23 1RN054A CN-1574-1.1 D09 3 B ACT Butterfly MO ST-Q Pt 23 1RN057A CN-1574-1.1 DOS 3 B ACT Butterfly MO. ST-Q PI 23 1RN058B CN-1574-1.1 D11 3 B ACT Butterfly MO ST-Q Pl 23 1RN063A CN-1574-1.1 D08 3 B ACT Butterfly MO ST-Q Pt 23 1RN8438 CN-1574-1.1 DOS 3 B ACT Butterfly MO ST-Q PI 23 i l l t. i i I Section 3.2 SHARED - 1 of 1 Rev. 23 06/29/96 l
. . . = . -. .
M - A s Unit 1 - Catawba Nuclear Station Inservice Testing Program
.i TEST . TEST ROW 8 LOW ASME VMVE ACT ACT ' nEQwT ' REQWT ' ~ JUSTIF FOR ' TEST vavE muusm osaana coon etAss cATony ras vavE Tm Tm mo.1 mo. neuu ntesT oEFenn naamans noenmanws mEv -
STEAM GENERATOR BLOWDOWN RECYCLE (88) 1B0008A CN-1580-1.0 KOS 2 B ACT Gate MO ST-Q PI 23 1B00100 CN-1580-1.0 K07 2 B ACT Gate MO ST-Q Pt 23 188019A CN-1580-1.0 COS 2 B ACT Gate MO ST-Q Pt 23 188021B CN-1580-1.0 C07 2 B ACT~ Gate MO ST-Q PI 23 '; 4
'1B0056A CN-1580-1.0 HOS 2 B ACT Gate MO ST-Q Pt 23 188057B CN-1560-1.0 H07 2 B ACT Gate MO ST-Q PI '23_
1BB060A CN-1580-1.0 F05 2 B ACT Gate MO ST-Q PI 23
- 1BB061B CN-1580-1.0 F07 2 B ACT Gate MO ST-Q Pl 23_
188147B. CN-1580-1.0 K07 2 B ACT Globe MO ST-Q PI 23 1B81488 CN-1580-1.0 - H07 2 B ACT Globe MO ST-Q Pl 23_ , 1B81498 CN-1580-1.0 F07 2 B ACT Globe MO ST-Q Pl 23 1881508 CN-1580-1.0 C07 2 B ACT Globe MO ST-Q Pi 23 Section 3.2 BB- 1 of 1 Rev.23 06/29/96
+ .___-m_ ____.______-m.____ _ _ _ _ _ _ - _ . _ _ . _ _ m _ -_ - _ - _ _ _ . _ _ __m -_-_m - - - _ _ _ _____._-_m- - _ _ _ ier
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' J .
t I' Unit 1 - Catawba Nuclear Station < Inservice Testing Program TEST , TEST ACT REQ wT REQwT .JUSTtFPOR TEST t PLOW FLOW AsheE VALVE ACT PAS ' VALVE TYPE TYPE 9s0.1 tuo. 2 REUEF REOST DEFWWIAL RERAAfulS ' ALTWWGATlWES REV _ ., OtAGRAA8 COOR CLASS CATGRY {; VALwE esunstER .
+
AUXILIARY FEEDWATER SYSTEM (CA) l FSOK;-Q CN-CA-03 23 1CA006 CN-1592-1.0 DOS 3 C .ACT Check SA j D05 3 C ACT Check SA FSOK;-Q CN-CA-03 - 23 l 1CA010 CN-1592-1.0 3 C ACT Check SA FSOIC-Q CN-LA 23 .. l- 1CA012 CN-1592-1.0 D01 CN-1592-1.0 D02 3 B ACT Gate MO ST-Q Pi l. 1CA015A D06 3 B ACT Gate MO ST-Q - PI 23 l ,1CA0188 CN-1592-1.0 CN-1592-1.0 3 C ACT 3-Way SA FS 23 l
'1CA020 11 1 J10 3 C ACT Check SA FSOfC-Q 23 - .*
L - 1CA023 CN-1592-1.0
. CN-1592-1.0 3 C ACT 3-Way SA FS. . 23-l 1CA027 10 4 C Check SA FSOfC-Q 23; l- 1CA028 CN-1592-1.0 J03 3 ACT.
1CA032 CN-1592-1.0 10 8 3 C ACT 3-Way SA FS 23-CN-1592-1.0 -J07 3 C ACT Check SA FSOdC-Q 23 1CA033 CN-1592-1.1 C12 3 B ACT Globe AO( ST/FT-Q Pt 23 1CA036 CN-1592-1.1 - G12 2 C ACT Check SA FSOfC-Q CN-CA 23 1CA037 MO ST-Q Pl ~ 23: ! 1CA038A CN-1592-1.1 H12 2 B ACT Gate CN-1592-1.1 J12 3 B ACT Globe AO ST/FT-Q Pl. 23 1CA040 , , i 1CA041 CN-1592-1.1 11 2 2 C ACT Check SA FSOdC-Q : CN-CA-01 23 1CA042B CN-1592-1.1 11 2 2 B ACT . Gate MO ST-Q Pt 23 CN-1592-1.1 JO9 3 B ACT Globe AO ST/FT-Q Pl - 23 ! ' 1CA044 1CA045 CN-1592-1.1 J09 2 C ACT Check SA FSOfC-Q CN-CA 23-CN-1592-1.1 - 2 B ACT Gate MO ST-Q - Pt 23 ~ j 1CA0468 10 9
. 1CA048 CN-1592-1.1 C09 3 B ACT Globe AO ST/FT-Q Pt 23 1CA049- CN-1592-1.1 G09 2 C ACT Check SA FSO/C-Q CN-CA-01 . 23 i' 1CA050A CN-1592-1.1 H09 2 B ACT Gate MO ST-Q Pl , 1CA052 CN-1592-1.1 C06 3 B ACT Globe AO ST/FT-Q Pt _
23 ' 1CA053 CN-1592-1.1 G06 2 C ACT Check SA FSOfC-Q CN-CA-01 23 1CA0548 CN-1592-1.1 H06- 2 B ACT Gate MO ST-Q Pl 23 - i 1CA056 CN-1592-1.1 J06 3 B ACT Globe AO ST/FT-Q - Pl 23 1CA057 CN-1592-1.1 JOS 2 C ACT Check SA FSO/C-Q CN-CA-01 23 SecHon 3.2
.CA - 1 of 2 :
4 Rev. 23 06/29/96 1
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\ p Unit 1 - Catawba Nuclear Station '
insemce Testing Program .: TEST TEST ' . FLOW ' PLOW ASME VALVE ACT ACT REQwT - REOMT ' JUSTir FOR ' TEST DIAdmAAA COOR CLASS . CATORY , PAS VALVE TYPE ' TYPE. 10 0 .1 too. 2 - - RELIEF REOST DEP5WWL - fERAAfutS : ALT 5usAffwES IWV ..
- VALVE soundSER AUXILIARY FEEDWATER SYSTEM (CA) 1CA058A CN-1592-1.1 - 10 6 2 B ACT Gate MO' ST-Q . Pt '23 3 1CA000 CN-1592-1.1 J03 3 B ACT Globe AO ST/FT-Q ' PI :23-
'.1CA061 CN-1592-1.1 10 3 .2 C ACT Check SA- FSOC-Q . CN-CA 01 23 1CA062A- CN-1592-1.1 10 3 - 2 B ACT ' Gate - MO ST-Q P1 23
~1CA064 CN-1592-1.1 C03 3 B ACT Globe .AO ST/FT-Q Pt '23.
-1CA065' CN-1592-1.1 - G03 2 C ACT Check SA ' FSOC-Q CN-CA-01 23i 1CA006B CN-1592-1.1 H03 2 B ACT Gate MO ST-Q - Pi - . 23 L 1CA085B CN-1592-1.0 - D07 3 B ACT Gate MO ST-Q Pi . _ 23 .' ;
'I 1CA116A . CN-1592-1.0 DOS 3 B ACT Gate MO ST-Q Pt 23 -
1CA149 CN-1592-1.1 ' 10 1 2 B ACT Gate - AO ST/FT-Q ' Pi - 23'
.1CA150 CN-1592-1.1 10 5 2 B ACT Gate AO ST/FT-Q Pt 23:
1CA151 CN-1592-1.1 10 8 2 B ACT Gate AO ST/FT-Q PI 23 1CA152 CN-1592-1.1 11 1 2 B ACT Gate - AO ST/FT-Q PI '23 1CA171 CN-1592-1.0 C06 3 C ACT Check SA . FSOC-Q CN-CA-02 23. .! CN-CA-02 23 I 1CA172 CN-1592-1.0 : C08 3 C ACT Check SA FSOC-Q
-?'
' 1CA173 CN-1592-1.0 EOS 3 C ACT Check SA FSOC-Q CN-CA-04 -23
- 1CA185 CN-1592-1.1 E01 2 B ACT Gate AO ST/FT-Q ' Pt 23
' 1CA186 CN-1592-1.1 EOS 2 B ACT- Gate AO ST/FT-Q ' PI :23~
-1CA187 CN-1592-1.1 - E08- 2 B ACT Gate AO- ST/FT-Q PI 23: '
1CA188 CN-1592-1.1 E11 2 B ACT Gate AO ST/FT-Q Pl 23. 1 8 Section 3.2 CA - 2 of 2 Rev.23 06/29/96
- - _ , - - - . . .;-_.-- . . . _..i.. _ , . _ ~ . ~ . . . - . , . . , _ . . ,,
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"h (O v v Unit 1 -Catawba Nuclear Stabon Inservice Testing Program TEST TEST FLOW FLOW ASME VALVE' ACT ACT REQWT - REQWT JUSTIF FOR TEST '
VALVE NUMBER DMGRAM COOR CLASS CATGRY - PAS VALVE TYPE TYPE NO 1 ' NO. 2 RELEF REOST DEFERRAL., REMMMS ALTERNATfWES REV FEEDWATER SYSTERE (CF) 1CF031 CN-1591-1.1 G13 2 C ACT Check SA FSC-Q 23 1CF033 CN-1591-1.1 F13 2 B ACT Gate . HO STFT-O Pl CN-CF 23 - -t 1CF040 CN-1591-1.1 G09 2 C ACT Check SA FRJ-Q : 23 1CF042 CN-1591-1.1 F09 2 B ACT Gate HO STET-Q PI CN-CF-01 23 1CF049 CN-1591-1.1 G06 2 C ACT Check SA FSC-Q - . 23 1CF051 CN-1591-1.1 F06 2 B ACT Gale HO STFT-Q Pl CN-CF-01 23 1CF058 CN-1591-1.1 G03 2 C ACT Check SA FSC-Q 23 ; 1CF060 CN-1591-1.1 F03 2 B ACT Gate HO STET-Q Pl ~ CN-CF-01 23 ' 1CF087 CN-1591-1.1 F02 2 B ACT Gate AO STET-Q Pl 23-1CF088 CN-1591-1.1 F06 2 8 ACT Gate AO STFT-Q - Pt 23 1CF089 CN-1591-1.1 F09 2 B ACT Gate AO STFT-Q Pt 23 1CF090 CN-1591-1.1 F13 2 B ACT Gate AO STNT-Q Pi' 23
~
Section 3.2 CF - 1 of 1 Rev. 23 06/29/96
O J O Unit 1 - Catawba Nuclear Station Inserwce Teshng Program-Test TEST Plow ' Flow Asast VALVE ACT ACT MGMT MQwT JUSTeP POR Test .
% ALVE 98URASER DIAGRAAA COOR CLASS CATGRY. pas VALVE TYPE TYPE 80 0 .1 00 0 . 2 REUEF MOST DEFEfUtAL RERAAfuls . ALTsusATIVES MV-DIESEL GENERATOR ENG8NE FUEL OIL SYSTEM (FD) 1FD022 CN-1609-3.0 J13 3 B ACT Globe SO ST/FT-Q 23 iFD029 CN-1609-3.0 F05 3' C ACT Check SA FSO/C-Q 23 '1FD034 CN-1609-3.0 H13 3 C ACT Rehof SA RV 40 PSIG 23 1FD062 CN-1609-3.1 J12 3 B ACT Globe SO ST/FT-Q -23 1FD069' CN-1609-3.1 -FOS 3 C ACT Check SA FSO/C-Q 23 1FD074 CN-1609-3.1 H13 3 C ACT Relief SA RV 40 PSIG ' 23-Section 3.2 FD - 1 of 1 Rev.23 06/29/96 -
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Unit 1 - Catawba Nuclear Station Inservice Testing Program TEST TEST ASME VALVE ACT ACT MQWT REQ WT JUST1F FOR TEST PLOW PLOW COOR CLASS CATORY PAS VALVE TYPE TYPE 80 0 .1 90 0 . 2 REUE7 REOST DEF94WL REMAfuls ALTEfesAftvES MV VALVE 90VMSER DeAGRAM REFUEUNG WATER SYSTEM (FW) CN-1571-1.0 J13 2 B ACT Gate MO ST-Q Pt 23 , 1FWOO1A 1FWOO4 CN-1871-1.0 LO7 2 A PAS Gate MA U 23 , 1FWOOS ' CN-1571-1.0 LOS 2 NC PAS Check SA U 23 1FWO11 CN-1571-1.0 J04 2 A ACT Plug MA U 23 1FWO13 CN-1571-1.0 JOS 2 A ACT Plug 'MA U 23 1FWO27A CN-1571-1.0 F03 2 B ACT Gate MO ST-Q Pt 23 1FWC28 CN-1571-1.0 F02 2 C ACT Check SA FSO/C-Q CN-FW-01 23 1FWO32B CN-1571-1.0 J13 2 B ACT Gate MO ST-Q Pl 23 1FWO33A CN-1571-1'.0 B11 2 B ACT Globe MO ST-Q Pt 23. 1FWO49B CN-1571-1.0 B07 2 B ACT Globe MO ST-Q Pl : 23 1FWOS2 CN-1571-1.0 E10 - C ACT Check SA FSO4 23- ; 1FWO55B CN-1571-1.0 H03 2 B ACT Gate MO ST-Q Pt 23 1FWOS6 CN-1571-1.0 H02 2 C ACT Check SA FSO/C-Q CNF#-01 23 i i t a Section 3.2 N - 1 of 1 Rev. 23 06/29/96
Unit 1 - Catawba Nuclear Station Inservice Testing Program TEST TEST VALVE ACT ACT RFQ WT REQ WT JUSTtF FOR TEST FLOW FLOW Ash 4E
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CN-1499-IA1.01 2 A/C ACT Check SA FSC-Q U CN-IA-01 23 IIACV5340 CN-1499-IA1.01 2 A/C ACT' Check SA FSC-Q U CN-IA-01 23 11ACV5350
'i CN-1499-IA1.01 2 A/C ACT Check SA FS"-Q U CN-IA-01 23 ilACV5360 CN-1499-IA1.01 2 A/C ACT Check SA FSC-Q U CN-IA-01 23 11ACV5370 11ACV5380 CN-1491NA1.01 2 A/C ACT Check SA FSC-Q U CN-IA-01 ~ 23 11ACV5390 CN-1499-IA1.01 2 A/C ACT Check SA FSC-Q U CN-IA-01 23 1
' 11ASV5080 CN-1499-IA1.01 2 A ACT Globe SO . ST/FT-Q U/PI 23 ilASV5160 CN-1499-IA1.01 2 A ACT Globe SO ST/FT-Q U/PI 23 11ASV5400 CN-1499-IA1.01 2 A ACT Globe SO ST/FT-Q - U/P1 23 11ASV5410 CN-1499-IA1.01 2 A ACT Globe SO ST/FT-Q U/Pi 23 Section 3.2 IA - 1 of 1 Rev.23 06/29/96
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1KC3388 CN-1573-1.3 D12 2 B ACT- Gate MO ST-Q PI- CN-KC-02 23 1KC340 CN-1573-1.3 E12 2 A/C ACT Check SA FSC-Q - U CN-KC-03 23 CN-1573-1.3 LOS 2 B ACT Gate MO ST-Q Pi . CN-KC-02 . -23 1KC424B 1KC425A CN-1573-1.3 LO6 2 B ACT Gate MO ST-Q : Pi CN-KC-02 23 j ' KC - 1 of 2 ! Sechon 3.2 Rev.23 06/29/96 1
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Unit 1 - Catawba Nuclear Station inserwce Testmg Program TEST 1EST 3 FLOW FLOW AsheE VALVE ACT ACT REQW T REC"tsT JUSTIF FOR TEST COOR CLASS CATORY PAS VMVE TYPE TYPE 90 0 .1 asO. 2 REUEF R**JST DEF9WIAL RERRARKS ALTUW8ATIVES . REV , VMVE psubdBER . DIAGRAfd COMPONENT COOUNG (KC) 1KC429B CN-1573-1.5 H02 2 A ACT Globe MO ST-Q LJ/PI . 23 1KC430A CN-1573-1.5 J03 2 A ACT Globe MO ST-Q LJ/Pi 23 - 1KCC37A CN-1573-1.0 C03 3 B ACT Globe MO STO/C-Q PI 23 1KCC40B CN-1573-1.0 C10 3 B ACT Globe MO STO/C-Q Pl . 23 .
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. -1 Unit 1 - Catawba Nuclear Station Insennce Testing Program j si TEST TEST PLOW ASME VALVE ACT ACT RE0wT MQwT JUSTIF POR TEST.
Flow COOR CLASS CATORY PAS VALVE TYPE TYPE ' 5e0.1 00 0 . 2 REUEF REQST DEP5WW REMAfutS ALTUWeATIVES MV VALVE touteSER DRAGRAM DtESEL GENERATOR ENGINE COOUNG WATER SYSTEM (KD) CN-1609-1.0 J10 3 C ACT . Check SA FSOC-Q CN-KD-01 23 1KD006 1KD021 CN-1609-1.0 E10 3 C ACT Check SA ' ' FSOC-Q CN-KD-01 23 i i
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DLAGRMA COOR CLASS .CATGRY ' PAS VALVE TYPE TYPE 30 0 .1 98 0 . 2 REUEFREQST DEFEfWIAL REMAAKS ALT 5WeATIVES REV - - VALVEfeUMeER SPENT FUEL COOLWG (KF) ~ 1KF101B CN-1570-1.0 H13 2 B ACT Gate - MO ST-Q Pi- 23 ' 1KF103A CN-1570-1.0 H12 2 B ACT Gate MO ST-Q PI 23 . 9 1 i Section 3.2 KF- 1 of 1 Rev. 23 06/29/96
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O O 0: Unit 1 - Catawba Nuclear Station Inservice Testeg Program TEST TEST . FLOW FLOW ASaAE VALVE ACT ACT. REQ WY RECMT - JUSTIF FOR TEST VALVE tsUhetER DRAGRAM COOR- CLASS CATGRY PAS VALVE TYPE TYPE 90 0 .1 WO. 2 REUEF REOST DEFEMAL REhsAfEs ALTERNATIVES IWV RADIATION MONITORS (MI) 1MIMV6470 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23 1MIMV6471 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23-1MIMV6480 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23 1MIMV6481 CN-1499.03-09.02 K10 2 A ACT Needle MA U ~23 1MIMV6490 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23 i 1MIMV6491 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23 -1MISV5230 CN-1499-Ml19 - 2 A ACT' Globe SO ST/FT-Q U/PI 23 ' 1MISV5231 CN-1499-M119 2 A ACT Globe SO ST/FT-Q U/PI 23 1MISV5232 CN-1499-M119 2 A ACT Globe SO ST/FT-Q U/Pt -23 1MISV5233 CN-1499-M119 2 A ACT Globe SO ST/FT-Q U/PI 23 t Section 3.2 M - 1 Of I Rev.23 06/29/96
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Unit 1 - Catawba Nuclear Station Inservice Testing Program TEST TEST
. FLOW FLOW ASME VALVE ACT ACT MQwT MQwT JUSTtF POR TEST COOR CLASS CATORY PAS VALVE TYPE TYPE 30 0 .1 50 0 . 2 REUEF MOST OEFERRAL REMAfutS . ALTEpueATIVES ' REV VALVE ISUMBER DiMIRAM REACTOR COOT. ANT SYSTEM (NC) 23 1NC001 CN-1553-1.1 K03 1 C ACT Relief SA RV 2485 PSIG ' 23 1NC002 CN-1553-1.1 K04 1' C ACT Relief SA RV 2485 PSIG 23 1NC003 CN-1553-1.1 K06 1 C ACT Relief SA RV 2485 PSIG 23 1NC031B CN-1553-1.1 F04 1 B ACT Gate MO ST-Q PI '23 1NCO32B CN-1553-1.1 G04 1 B ACT Globe AO ST/FT-Q Pl CN-NC-02 23 1NC033A CN-1553-1.1 F03 1 B ACT Gate MO ST-Q Pt 23
, 1NC034A CN-1553-1.1 G03 1 B ACT Globe AO ST/FT-Q Pi CN-NC 23 1NCO358 CN-1553-1.1 F02 1 B ACT Gate MO ST-Q Pt 23-1NC0368 CN-1553-1.1 G02 1 B ACT Globe AO ST/FT-Q Pl CN-NC-02 23 1NC0538 CN-1553-1.1 K11 2 A ACT Globe MO ST-Q U/Pt -23 1NC054A CN-1553-1.1 KD9 2 A ACT Globe MO ST-Q U/PI 23 , 1NC056B CN-1553-1.1 11 3 2 A ACT Gate MO ST-Q U/Pl 23 1NC057 CN-1553-1.1 11 2 2 A/C PAS Check SA FSO/C-Q U CN-NC 23 1NC141 CN-1553-1.3 JO8 2 A PAS Gate MA U 23 1NC142 CN-1553-1.3 K08 2 A PAS Gate MA U 23: 1NC1958 CN-1553-1.3 D07 2 A ACT Gate MO ST-Q U/PI 23 1NC196A CN-1553-1.3 D07 2 A ACT Gate MO ST-Q U/Pl 23 1NC250A CN-1553-1.1 LO7 1 B ACT Globe MO ST-Q Pi CN-NC-03 23 1NC251B CN-1553-1.1 LO6 1 B ACT Globe MO ST-Q - Pi CN-NC-03 23- ; 1NC252B CN-1553-1.1 K07 1 B ACT Globe MO ST-Q Pi CN-NC-03 23 1NC253A CN-1553-1.1 K06 1 B ACT Globe MO ST-Q Pl CN-NC-03 ' 23 i Section 3.2 NC - 1 of 1 Rev. 23 06/29/96 !
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O Unit 1 - Catawba Nudear Station Inservice Testing Program TEST TEST VALVE ACT ACT MQWT MQwT JUSTW FOR TEST FLOW FLOW ASME PAS VALVE TYPE TYPE NO.1 NO.2 REUEF MOST DEFEPAAL RSAAMLS ALTERNATWEs My VALVE NUMBER DIAGRAM COOR CLASS CATGRY RESIDUAL HEAT REMOVAL (ND) 1ND001B CN-1561-1.0 L13 1 A ACT Gate MO. ST-Q LT/PI CN-ND-01 '23 1ND002A CN-1561-1.0 'J13 1 A ACT Gate MO ST-Q LT/PI- CN-ND-01 23-CN-1561-1.0 2 C PAS Relief SA RV 450 PSIG 23 1ND003 11 3 CN-1561-1.0 G10 2 C ACT Check SA FSO/C-Q CN-ND-03 23 1ND010 CN-1561-1.0 E13 2 B ACT Globe MO ST-Q Pt 23 1ND025A CN-1561-1.0 G04 2 B ACT Butterfly AO ST/FT-Q PI 23 1ND026 1ND027 CN-1561-1.0 J06 2 ~B ACT Butterfly AO STiFT-Q Pl 23 CN-1561-1.0 H04 2 B ACT Gate MO ST-Q Pl CN-ND-05 23 1ND028A 1ND031 - CN-1561-1.0 G02 2 .C PAS Relief SA RV 600 PSIG 23 CN-1561-1.0 F03 2 B ACT Gate MO ST-Q PI CN-ND-04 23 1ND032A CN-1561-1.0 D02 2 C PAS Relief SA RV 600 PSIG 23 1ND035 CN-1561-1.1 L13 A ACT Gate MO ST-Q LT/PI CN-ND-02 23 1ND036B 1 CN-1561-1.1 J13 A ACT Gate MO ST-Q LT/PI CN-ND-02 23 1ND037A 1 1ND038 CN-1561-1.1 11 3 2 C PAS Relief SA RV 450 PSIG 23 CN-1561-1.1 G10 2 C ACT Check SA FSO/C-Q CN-ND-03 23 - 1ND044 CN-1561-1.1 E13 2 B ACT Globe MO ST-Q PI 23 1ND0598 CN-1561-1.1 G04 2 B ACT Butterfly AO ST/FT-Q Pl 23 1ND060 CN-1561-1.1 J06 2 B ACT Butterfly AO ST/FT-Q PI 23 1ND061 CN-1561-1.1 H02 2 C PAS Relief SA RV 600 PSIG 23 1ND064 CN-1561-1.1 E03 2 B ACT Gate MO ST-Q PI CN-ND-04 23 1ND065B ND - 1 of 1 Section 3.2 06/29/96 Rev. 23
Unit 1 - Catawba Nudear Station . Inservice Testing Pmgram TEST TEST l FLOW ' FLOW ASME VALVE ACT ACT MOWT MOwT ' JUSTtF FOR TEST MRHfES 'ALTsueATIVES DEV VALVE NUMMR DIAORAM COOR CLASS CATGRY PAS VALVE TYPE TfPE 90 0 .1 NO. 2 REUEF REOST - DEFEMAL ICE CONDENSER REFRIGERATION (NF) CN-1558-2.0 H14 2 A ACT Gate AO ST/FT-Q U/P1 - 23
- 1NF228A 1NF229 CN-1558-2.0 F14 2 NC ACT Check SA FSC-Q U CN-NF-01 23 1NF2338 CN-1558-2.0 L10 2 A ACT Gate MO ST-Q - LJ/PI - 23.
1NF234A CN-1558-2.0 L12 2 A ACT Gate AO ST/FT-Q LJ/Pi 23 1NF235 CN-1558-2.0 - K10 2 NC ACT Check SA FSO/C-Q U 23 ' Section 3.2 NF- 1 of 1 Rev. 23 06/29/96 'l __ _ _ _ _ _ _ _ _ _ _ _ ____m_r--__ _m _ _ _ _ _ _ _ -. _ w w-vr r- ,,
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1N1070 1N1071 CN-1562-1.1 C05 1 A/C ACT Check SA FSO#CC LT CN-Ni-04 '23 CN-1562-1.1 G07 1 B ACT Gate MO Pt 23 1N1076A CN-1562-1.1 D07 1 A/C ACT Check SA FSOfC-Q LT CN-Ni 23 l , 1N1061 CN-1562-1.1 C07 1 AlC ACT Check SA FSO/C-Q LT CN-NI-04 23 ; 1NIO62 ~ G10 B ACT Gate MO Pi 23 ; 1N10688 CN-1562-1.1 1 ,
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1N1094 i CN-1562-1.1 F13 2 A ACT Gate MO ST-Q LJ/PI 23 - ) 1N1095A 1Nt0968 CN-1562-1.1 H13 2 A ACT Globe MO ST-Q LJtPI 23-CN-1562-1.2 G13 2 B ACT Gate MO ST-Q Pi- ' CN-NI-06 23 1N11008. CN-1562-1.2 G13 2 C ACT Check SA FSOC-Q CN-N1-07 23 1N1101 H14 2 C PAS Relief SA RV 220 PSIG 23 - 1N1102 CN-1562-1.2 2 B ACT Gate MO ST-Q ' Pi ' 23 - 1N1103A CN-1562-1.2 11 3 CN-1562-1.2 10 8 2 C ACT Check SA FSO/C-Q 23' ~i 1NB114 ~ NI- 1 of 4 - .; Section 3.2 Rev.23 06/29/96 '! t I
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1Nt176 ~ CN-1562-1.3 F09 1 A/C ACT Check SA FSOfC-Q LT CN-NI-14 23} ; 1N11788 CN-1562-1.3 E04 2 B ACT Gate MO ST-Q Pi CN-Ni-15 : 23 1N1180 CN-1562-1.3 F05 1 AIC ACT Check SA FSOE-Q LT CN-NI-14 . 23 L 1N1181 CN-1562-1.3 F04 1 A/C ACT Check SA - FSOtC-Q LT CN-Ni-14 ' - 23 1N11838 CN-1562-1.2 G04 2 B ACT Gate MO ST-Q . Pl CN-N1-16 23 4 1Nt1848 CN-1562-1.3 C10 2 B ACT Gate - MO. ST-Q Pi CN-NI-17 .23 1N1185A CN-1562-1.3 C05 2 B ACT Gate MO ST-Q Pi CN-N1-17 ' 23? i 1N1332A CN-1562-1.2 L12 2 B ACT Gate MO ST-Q Pl CN-NI = 23' - 1NI3338 CN-1562-1.2 K12 2 B ACT Gate MO ST-Q Pl CN-NI-18 ' 23 - j 1N1334B . CN-1562-1.2 K11 2 B ACT Gate MO ST-Q P1 CN-NI-23 , 23 ,l j 1N1342 CN-1562-1.2 D13 2 C ACT Check SA FSO/C-Q CN-NI 23 -- 1N1351 CN-1562-1.0 11 0 1 C ACT Check SA FSO/C-Q CN-NG-03 23 1N1352 CN-1562-1.0 10 9 1 C ACT Check SA FSOIC-Q CN-NI-03 23 CN-Ni-03 .23~ ; 1N1353 CN-1562-1.0 10 7 1 C ACT Check SA FSOtC43 1NI354 CN-1562-1.0 10 5 1- C ACT Check SA FSOtC-Q CN-NI-03 . 23 1N1391 CN-1562-1.1 CO3 2 A ACT Globe AO LT 23! { 1N1392 CN-1562-1.1 C04 2 A ACT- Globe AO LT 23.
'1N1393 CN-1562-1.1 C08 2 A ACT Globe AO LT 123-1N1394 CN-1562-1.1 C11 2 A ACT Globe AO LT :23
- 1N1395 CN-1562-1.2 E01 2 A ACT Globe AO LT [23' .
Section 3.2 NI- 3 of 4 - 06/29/96 a Rev.23 , _ _ _ _ _- _ _ .e _. _ _ . _ . _ ~-m . _ . _ _, .& -.. .__2 , ~ _ _ _ _ _ _ _ _ _ _ _ _ _ m.+s m _ _ -i_m________ . _ _ _ . _ _ _ . - _ _ _ _ - _u___
m _ _ _ . . . __ _ .. _ . . ~ . - . - - . . . _ . . _ _ _ _ . .. . . _ . . . . . ._ ._. _. . . . . ._ _ . . _ . _ . _ . l Unit 1 - Catawba Nuclear Station Insesvice Testing Program TEST TEST ' ACT -ACT MQwT MOWT JusTW FOR TEST PLOW FLOW ASME VALVE . No.1 90 0 . 2 - AB.lEF REost DEPeutAL F.EBAAppts ALTEpusATIVES stEV VALVE tsubdBER DtAGRAad COOR CLASS -CATORY PAS VALVE TYPE TYPE SAFETY INJECTION SYSTEM (NI)
' K01 2 A ACT Globe AO LT 23 1N1396 CN-1562-1.2 2 A ACT Globe AO LT 23 1N1397 CN-1562-1.2 10 1 ~
CN-1562-1.2 C01 2 A ACT Globe AO LT 23-1N1396 CN-1562-1.1 K02 2 B ACT Globe MO ST-Q PI 23 1N1438A 1NI439B CN-1562-1.1 K05 2 B ACT Globe MO ST-Q PI '23 CN-1562-1.1 F13 2 A ACT Check SA U 23 1N1471 t Section 3.2 NE - 4 of 4 Rev. 23 M9/96
Unit 1 - Catawba Nuclear Station Inservice Testing Program TEST ' TEST FLOW FLOW ASME VALVE ACT ACT MQ'MT REQWT JUSTIF FOR TEST VALVE ssVMSER DeAGRAM COOR CLASS CATORY PAS VALVE TYPE TYPE 80 0 .1 B00. 2 REUEF MOST DEFERRAL REMMULS . ALTERNATIVES MV NUCLEAR SAMPLING SYSTEM (NM) 1NM'003A CN-1572-1.0 K03 2 A ACT Globe MO ST-Q U/PI 23 1NM006A CN-1572-1.0 J03 2- A ACT Globe MO ST-Q U/PI 23 1NM007B CN-1572-1.0 K06 2 A ACT Globe MO ST-Q U/P1 23 1NM022A CN-1572-1.0 J12 2 A ACT Globe MO ST-Q U/PI 23 1NM025A CN-1572-1.0 K12 2 A ACT Globe MO ST-Q U/PI 23 1NM0268 CN-1572-1.0 K08 2 A ACT Globe MO ST-Q U/PI 23 1NM069 ' CN-1572-1.1 G09 2 A ACT Relief SA U RV 700 PSIG 23 1NM072B CN-1572-1.1 106 2 A ACT Globe MO ST-Q U/PI 23 1NM0758 CN-1572-1.1 108 2 A ACT Globe MO ST-Q U/PI 23 1NM0788 CN-1572-1.1 109 2 A ACT Globe MO ST-Q U/PI 23 1NM0818 CN-1572-1.1 11 1 2 A ACT Globe MO ST-Q U/Pi 23 1NM082A CN-1572-1.1 E09 2 A ACT Globe MO ST-Q U/PI 23 1NM187A CN-1572-1.4 K02 2 B ACT Globe MO ST-Q PI 23 1NM190A CN-1572-1.4 K02 2 B ACT Globe MO ST-C Pi 23 1NM1918 CN-1572-1.4 10 2 2 B ACT Globe MO S T-Q Pl 23 1NM197B CN-1572-1.4 K05 2 B ACT Globe MO ST-Q PI 23 1NM2008 CN-1572-1.4 K06 2 B ACT Globe MO ST C PI 23 1NM201A CN-1572-1.4 106 2 B ACT Globe MO ST-G Pt 23 1NM207A CN-1572-1.4 K08 2 B ACT Globe MO ST-Q Pi 23 1NM210A CN-1572-1.4 K09 2 B ACT Globe MO ST-Q Pt 23 1NM211B CN-1572-1.4 10 9 2 B ACT Globe MO ST-Q Pt 23 1NM217B CN-1572-1.4 K11 2 B ACT Globe MO ST-Q PI 23 1NM220B CN-1572-1.4 K12 2 B ACT Globe MO ST-Q PI 23 1NM221A CN-1572-1.4 11 2 2 B ACT Globe MO ST-Q Pt 23 1NM424 CN-1572-1.0 10 3 2 NC ACT Check SA FSC-Q U 23 1NM425 CN-1572-1.0 K12 2 NC ACT Check SA FSC-Q U- 23 Section 3.2 NM - 1 of 1 Rev. 23 06/29/96 .
O ~ O 0; Unit 1 - Catawba Nuclear Station . Inservice Testing Program . TEST TEST FLOW ASME VALVE ACT ACT REQ wT REQWT - JUSTar FOR TEST FLOW COOR CLASS CATORY PAS VALVE TYPE TYPE aso.1 00 0 . 2 RELIEF REOST DEFWWIAL REMAf4LS ALfWWGATIVES REV VALVE 96UMetR DLAGRMA
- CONTAINMENT SPRAY (NS) 1NS001B CN-1563-1.0 C13 2 B ACT Gate MO ST-Q Pi 23 1NS0038 CN-1563-1.0 E13 2 B ACT Gate MO ST-Q PI '23 1NS004 CN-1563-1.0 D13 2 C ACT Check SA FSCWC-Q CN-NS 23 1NS012B CN-1563-1.0 C05 2 B ACT Gate MO ST-Q Pt 23 1NS013 CN-1563-1.0 C03 2 C ACT Check SA FSO/C-Q CN-NS-02 23
; 1NS0158 CN-1563-1.0 E05 2 B ACT Gate MO ST-Q PI 23 1NS016 CN-1563-1.0 E03 2 C ACT Check SA FSO/C-Q CN-NS-02 23 1NS018A CN-1563-1.0 J13 2 B ACT Gate MO ST-Q PI 23 ;
1NS020A CN-1563-1.0 11 3 2 B ACT Gate MO ST-Q PI 23 1NS021 CN-1563-1.0 11 3 2 'C ACT Check SA FSO/C-Q CN-NS-01 23 1NS029A CN-1563-1.0 10 5 2 B ACT Gate MO ST-Q Pt 23 1NS030 CN-1563-1.0 102 2 C ACT Check SA FSO/C-Q CN-NS-02 23 1NS032A CN-1563-1.0 K05 2 B ACT Gate MO ST-Q Pt 23 1NS033 CN-1563-1.0 K03 2 C ACT Check SA FSO/C-Q CN-NS-02 23 1NS038B CN-1563-1.0 F05 2 B ACT Gate MO ST-Q Pi CN-NS-03 23 1NSO41 CN-1563-1.0 F03 2 C ACT Check SA FSO/C-Q CN-NS-02 23 ' 1NSO43A CN-1563-1.0 HOS 2 B ACT Gate MO ST-Q Pi CN-NS-03 23 1NSO46 CN-1563-1.0 H03 2 C ACT Check SA FSO/C-Q CN-NS-02 23 1NSO98 CN-1563-1.0 J09 2 C ACT Check SA FSO/C-Q CN-NS 23
-1NSO99 CN-1563-1.0 D09 2 C ACT Check SA FSO/C-Q CN-NS-01 23 NS - 1 of 1 Section 3.2 Rev. 23 06/29/96
_ _ _ - _ _ _ _ _ _ _ = _ _ - - _ _ _ _ - _ _ - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - - - _ _ _ . _ _ _ . _ - _ _ _ _
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1NV014 CN-1554-1.0 F09 2 A ACT 1.J 2 'A ACT Globe MO ST-Q l.J/PI CN-NV-01 23 - ; 1NV015B CN-1554-1.0 H10 CN-1554-1.0 C08 2 C ACT Relief -SA RV- 150 PSIG 23-1NV087 B10 2 B ACT Gate MO ST-Q Pl CN-NV-02 . 23 1NV069A CN-1554-1.0 D10 2 A/C ACT Check SA FSC-Q LJ 23' 1NV000 CN-1554-1.0 B12 2 B ACT Gate MO ST-Q - Pl CN-NV-02 23 ' ; 1NV091B CN-1554-1.0 ' CN-1554-1.1 C05 2 B ACT Gate MO ST-Q PI CN-NV-03 23' i= 1NV188A 1NV1898 CN-1554-1.1 C04 2 B ACT Gate MO ST-Q Pi CN-NV-03 23:
- CN-1554-1.6 D01 2 B ACT Globe MO ST-Q PI CN-NV-07 23 ' j
' 1NV202B CN-1554-1.6 D02 2 B ACT Globe MO ST-Q Pi CN-NV.07 23 '
' 1NV203A ~
CN-1554-1.1 G04 2 C ACT ' Relief SA RV 150 PSIG -[ 1NV205 CN-1554-1.6 D03 2 B ACT Plug AO Pt 23 ' 1NV206 CN-1554-1.6 D06 .2 B ACT Plug AO PI 23 1NV218 ' ' CN-1554-1.1 G04 2 C ACT Check SA FSO-Q 23 1NV220 CN-1554-1.1 E06 2 C ACT Relief SA RV 220 PSIG - 23 - l 1NV222 CN-1554-1.1 H07 2 C ACT Relief SA RV 75 PSIG 23 1NV223 1NV252A CN-1554-1.7 K11 2 B ACT Gate MO ST-Q Pl CN-NV-10 23- i CN-1554-1.7 K12 2 B ACT Gate MO ST-Q Pi CN-NV-10 23 j 1NV253B 1NV254 CN-1554-1.7 K12 2 C ACT Check SA FSO/C-Q CN-NV 23' j CN-1554-1.7 2 C ACT Check SA FSO/C-Q 23 ~! 1NV268 10 5 CN-1554-1.7 2 C ACT Check SA FSO/C-Q CN-NV-06 23 . 1NV270 10 5 ; 1NV273 CN-1554-1.7 E14 2 C ACT Relief SA RV 220 PSIG '23 CN-1554-1.7 EOS 2 C ACT Check SA FSO/C-Q 23 1NV288 l [ Section 3.2 NV - 1 of 2 - Rev.23 06/29/96
.. . - . ~ .- ..- . . .. . - .. . . . - . .. .. . - . . .
D ' f'~N, - U l { Unit 1 - Catawba Nuclear Station l Inservice Testin0 Program l TEST TEST ' REQWT JUSTIF FOR TEST FLOW ASME VALVE ACT ACT REQWT Flow REUEF REQST DEFSURAL ASAARKS ALTDesAfrWS REV Ct. ABS 'CATGNY PAS VALVE TYPE TYPE 30 0 .1 ~ 800. 2
-VALytfeutetet DeAGRMS COOR CHEMICAL & VOLUME CONTROL (NV)
SA FSO/C-Q CN-NV-06 23 1NV290 CN-1554-1.7 DOS -2 C -ACT Check ACT Gate MO ST-Q Pi CN-NV-04 :23 1NV312A CN-1554-1.2 K05 2 B 23 ' K06 2 B ACT Gate MO ST-Q Pi CN-NV-04 1NV3148 CN-1554-1.2 Check SA FSO/C-Q CN-NV-06 23 1 1NV813' CN-1554.1.7 C12 2 C ACT ACT Globe MO ST-Q - Pt 23 1NV865A CN-1554-1.8 H01 2 B MO ST-Q U/PI 23 1NV872A CN-1554-1.8 F08 2 A ACT Globe ACT Check SA FSC-Q U CN-NV-09 23 1NV874 CN-1554-1.8 F10 2 A!C k i NV - 2 of 2 Section 3.2 06/29/96 Rev.23 ; i
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o _ _ o ; Unit 1 -Catawba Nuclear Station insennce Testing Program TEST TEST PLOW ash 0E VALVE ACT ACT REG WT REQwT JusTF POR TEST
- PLOW VALVE 9NRADER DIAGRAAS COOR CLASS' CATeRY pas VALVE TYPE TYPE 90 0 .1 00 0 . 2 RELIEF MOST DEPWWIAL RSAAfuls ALTWueATWES .. MV CONTAINMENT PENETRATION VALVE INJECTION WATER SYSTEM (NW) j, C ACT Check SA FSO-Q CN-NW-01 23 ~ '!
1NWOO6 CN-1569-1.0 G11 2 1NWOO8A CN-1569-1.0 G13 '2 B ACT Gate SO. ST/FT-Q Pt 23-1NWO13A . ' CN-1560-1.0 EOS 2 B ACT Gate SO - ST/FT-Q Pl. ~ 23 -
.l 1NWD17 CN-1568-1.0 E11 2' .C ACT Check SA FSOCQ ~ CN-NW-02 23
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d 1NWO20A CN-1569-1.0 F09 2 B ACT - Gate SO ST/FT-Q Pt :23 1NWO21 - CN-1569-1.0 E12 2 C ACT Check SA FSOCQ CN-NW-02 23 .l 1NWO24 . CH-1569-1.0 E13 2 C ACT Check SA FSOCQ . CN-NW 23 1NWO27 CN-1569-1.0 E14 2 C ACT Check SA FSOCO CN-NW-02 23
- 1NWO35A CN-1569-1.0 H09 2 B ACT Globe MO ST-Q PI 23 1NWO37 CN-1569-1.0 10 9 2 C ACT Check SA FSOCQ CN-NW-02 23 1NWO40 CN-1569-1.0 J11' 2 C ACT Check SA FSOCQ CN-NW-02 23.
1NWO43 CN-1569-1.0 J10 2 C ACT Check SA FSOCQ CN-NW-02 23 1NWO46A CN-1569-1.0 K09 2 B ACT Gate SO ST/FT-Q Pl 23 1NWO47 CN-1569-1.0 L10 2 C ACT Check SA FSOCQ CN-NW-02 23 ' .,t
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1NWO50 CN-1569-1.0 L11 2 C ACT Check SA FSOCQ CN-NW-02 23 1NWO53 . CN-1569-1.0 L11 2 C ACT Check SA FSOCQ CN-NW-02 23' 1NWO61B CN-1569-1.0 G02 2 B ACT Gate SO ST/FT-Q Pt 23 1NWO63 CN-1569-1.0 G04 2 C ACT Check SA. FSO-Q CN-NW-01 23 1NWO688 CN-1569-1.0 EOS 2 B ACT Gate SO - ST/FT-Q - Pl 23 - 1NWO698 CN-1569-1.0 F06 2 B ACT Gate SO ST/FT-Q Pt . 23 ' 1NWO70 CN-1569-1.0 EOS 2 C ACT Check SA FSOCQ - CN-NW-02 - 23 1NWO74 CN-1569-1.0 EOS 2 C ACT Check SA FSOJC-Q CN-NW-02 23 1NWO77 CN-1569-1.0 E04 2 C ACT Check SA FSOCQ CN-NW 23 1NWO80 CN-1569-1.0 E03 2 C ACT Check SA FSOCQ CN-NW-02 _ ' 23 - 1NWO83 CN-1569-1.0 E02 2 C ACT Check SA FSOCQ CN-NW-02 23 1NWO86 CN-1569-1.0 E01 2 C ACT Check SA FSOCQ CN-NW-02 23 1NWO89 CN-1569-1.0 C05 2 C ACT Check SA FSO/C-Q CN-NW-02 ; . 23 1NWO92 CN-1569-1.0 C05 2 C ACT Check -SA FSOCQ CN-NW-02 23 , Section 3.2 NW - 1 of 5 Rev. 23 06/29/96-
- .. . .. . . . . m _ _ . - . . . _ - _ - _ . _ . . . . - - . .. _.._ _. . . . . - . _ _ _ ._ _ _ ,- Unit 1 - Catawba Nudear Station - Inservice Testing Program TEST- TEST AsesE VRVE ,ACT ACT REO MT MOWT JUSTir FOR TEST FLOW FLCMr
.COOR CLASS CATORY PAS VRVE TYPE TYPE 80 0 .1 90 0 . 2 REUEF MEOST ' DEFeWWL fWh8 ARKS ALT 1BusATIVES MV-VRVE esub8SER DIAGRAfd CONTAINMENT PENETRATION VALVE INJECTION WATER SYSTEM (NW) 1NWO95 CN-1569-1.0 ' C04 2 C ACT Check SA . FSO/C-Q CN-NW-02 23 CN-1569-1.0 . CO2 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NWO96 1NW101 CN-1569-1.0 C01 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW1058 CN-1569-1.0 H06 2 B ACT Globe MO ST-Q PI 23 1NW107 ' CN-1569-1.0 10 6 2 C ACT Check SA FSO/C-Q CN-NW-02 -23 1NW109 CN-1569-1.0 KOS 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW110B CN-1569-1.0 K06 2 B ACT Gate SO ST/FT-Q PI 23 1NW111 CN-1569-1.0 JOS 2 C ACT Check SA FSO/C-Q CN-NW-02 23 ' 1NW114 CN-1569-1.0 LOS 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW120 CN-1569-1.0 JOS 2 C ACT Check SA FSOtC-Q CN-NW-02 23 -
1NW121 CN-1569-1.0 E01 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW122 CN-1569-1.0 E02 2 C ACT Check SA FSO/C-Q CN-NW-02 '23 1NW123 CN-1569-1.0 E03 2 C ACT Check SA FSO/C-Q CN-NW-02 23 r
' 1NW124 CN-1569-1.0 E04 2 C ACT Check SA FSO/C-Q CN-NW-02 .23 -
1NW125 CN-1569-1.0 E05 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW126 CN-1569-1.0 EOS 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW127 CN-1569-1.0 C01 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW128 CN-1569-1.0 CO2 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW129 CN-1569-1.0 C04 2 C ACT Check SA FSO/C-Q CN-NW-02 23
.1NW130 CN-1569-1.0 C05 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW131 CN-1569-1.0 C05 2 C ACT Check SA FSO/C-Q CN-NW-02 . 23 -
1NW132 CN-1569-1.0 K10 2 C ACT Check SA FSO/C-Q CN-NW-02~ 23 1NW133 CN-1569-1.0 K11 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW134 CN-1569-1.0 K11 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW135 CN-1569-1.0 J10 2 C ACT- Check SA FSO/C-Q CN-NW-02 23 1NW136 CN-1569-1.0 J11 2 C ACT Check SA FSO/C-Q CN-NW-02 23: 1NW138 CN-1569-1.0 D11 2 C ACT Check SA FSOIC-Q CN-NW-02 . 23 1NW139 CN-1569-1.0 E12 2 C ACT Check SA- FSO/C-Q CN-NW-02 23 Section 3.2 NW - 2 of 5 Rev.23 06/29/96
._ . _ .. . _ _ __ - _ _ . . - . _ _ . - _- _- . _ . _ , _ . - _ . _ . . . _ . . . _- _ _ _ . . . _ . . . _ . . _ _ . - ~
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- Inserwce Teshng Program TEST TEST' '
FLOW FLOW ASME VALVE ACT ACT REO WT REQ wT - JUSTIF FOR . - TEST . VALVE peUMBER COOR CLASS CATORY , PAS VALVE TYPE TYPE 90 0 .1 ' 9BO. 2 fELIEF fWOST OEFWWML RDMfuLS ' ALTWWeAftWES ' REV DIAGRAM CONTAINMENT PENETRATION VALVE INJECTION WATER SYSTEM (NW) i 1NW140 CN-1569-1.0 E13 2 C ACT Check SA FSOC-Q CN-NW-02 23 1NW141 CN-1569-1.0 E14 2 C ACT Check SA- FSOC-Q CN-NW-02 23'
' 1NW1458 CN-1569-1.0 C05 2 B ACT Gate SO ST/FT-Q - PI 23
' 1NW1468 CN-1569-1.0 E02 2 B ACT Gate SO ST/FT-Q PI 23 1NW147 CN-1569-1.0 J07 2 C ACT Check SA FSO/C-Q CN-NW-02 ' 23 1NW148 CN-1569-1.0 J07 2 C ACT Check SA FSOC-Q CN-NW-02 : 23 :
' 1NW159 CN-1569-1.0 J12 2 C ACT Check SA FSOC-Q CN-NW-02 23 *
' 1NW160 CN-1569-1.0 J12 2 C ACT Check SA FSOC-Q CN-NW-02 ' 23 '
1NW163 CN-1569-1.0 K12 2 C ACT Check SA FSOC-Q CN-NW '23-1NW164 CN-1569-1.0 K12 2 -C ACT Check SA FSOC-Q CN-NW-02 1NW168 CN-1569-1.0 K13 2 C ACT Check SA FSOC-Q CN-NW-02 '23 1NW169 CN-1569-1.0 K13 2 C ACT Check SA FSO/C-Q CN-NW-02 - 23 1NW171 CN-1569-1.0 J13 2 C ACT Check SA FSOC-Q CN-NW42 23 ; 1NW172 CN-1569-1.0 J13 2 C ACT Check SA FSOC-Q CN-NW-02 23; ' ' 1NW175A CN-1569-1.0 C12 2 B ACT Gate SO ST/FT-Q Pt 23 1NW178 CN-1569-1.0 C12 2 'C ACT Check SA FSOC-Q CN-NW-02 '23 , 1NW179 CN-1569-1.0 C12 2 C ACT Check SA FSOC-Q CN-NW42 23. 1NW180A CN-1569-1.0 C13 2 B ACT Gate SO ST/FT-Q Pt 23 1NW183 CN-1569-1.0 C13 2 C ACT Check SA FSOC-Q CN-NW-02 1NW184 CN-1569-1.0 C13 2 C ACT Check SA FSOC-Q CN-NW-02 23
.1NW185A CN-1569-1.0 C13 2 B ACT Gate SO ST/FT-Q Pt 23 1NW188 CN-1569-1.0 C13 2 C ACT . Check SA- FSO/C-Q CN-NW-02 .23 ;
1NW189 CN-1569-1.0 C13 2 C ACT Check SA FSOC-Q CN-NW-02 23 1NW190A CN-1569-1.0 C14 2 B ACT Gate SO ST/FT-Q PI 23 j 1NW193 CN-1569-1.0 C14 2 C ACT Check SA ~ FSO/C-Q CN-NW-02 ' 23 - , 1NW194 CN-1569-1.0 C14 2 C ACT Check SA FSOC-Q CN-NW-02 - 23 1NW195A CN-1569-1.0 E08 2 B ACT Gate SO ST/FT-Q Pt 23 j 1NW196 CN-1569-1.0 F08 2 C ACT Check SA FSOC-Q CN-NW-02 ,. 23 Section 3.2 NW- 3 of 5 Rev.23 06/29/96 _ - .~ _ _ . _ _ _ _ . . . . _ . _ . . - _ _. , . __ _ . - , . __
O O O Unit 1 - Catawba Nuclear Station ' ! Inservice Testing Program now now Asus vatve Act act d$r dEwT sustie ron . nemams rest Attenwarrvus new v=ve wuusen cmAanam coon ctass cArony ras v=ve Tvre ivre no.s wo. z neuu nnost openna CONTAINMENT PENETRATION VALVE INJECTION WATER SYSTEM (NW) F08 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW197 CN-1569-1.0 CN-1569-1.0 E08 2 B ACT Gate SO ST/FT-Q Pt 23. 1NW200A CN-1569-1.0 E08 2 C ACT Check SA FSO/C-Q CN-NW-02 '23 1NW201 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW202 CN-1569-1.0 DOS E07 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW205 CN-1569-1.0 CN-1569-1.0 F07 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW206 CN-1569-1.0 E07 2 C ACT Check SA FSO/C-Q . CN-NW-02 23 1NW209 CN-1569-1.0 E07 2 C ACT Check SA FSO/C-Q CN-NW-02 23
'1NW210 CN-1569-1.0 C07 2 C ACT Check SA FSO/C-Q CN-NW-02 23-1NW213 CN-1569-1.0 C07 2 C ACT Check SA FSO/C-Q CN-NW-02 ' 23 1NW214 CN-1569-1.0 C08 2 B ACT Gate SO ST/FT-Q Pi 23 1NW2178 CN-1569-1.0 C08 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW218 CN-1569-1.0 C08 2 C ACT Check SA FSO/C-Q CN-NW-02 23 '
1NW219 CN-1569-1.0 C09 2 B ACT Gate SO ST/FT-Q PI 23 1NW222B CN-1569-1.0 C09 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW223 CN-1569-1.0 C09 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW224 CN-1569-1.0 C09 2 B ACT Gate SO ST/FT-Q PI 23 1NW227B CN-1569-1.0 C09 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW230 1NW231 CN-1569-1.0 C09 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW2328 CN-1569-1.0 C10 2 B ACT Gate SO ST/FT-Q PI 23 1NW235 CN-1569-1.0 C10 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW236 CN-1569-1.0 C10 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW2378 CN-1569-1.0 C11 2 B ACT Gate SO ST/FT-Q PI 23 1NW240 CN-1569-1.0 C11 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW241 CN-1569-1.0 C11 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW242B CN-1569-1.0 C11 2 B ACT Gate SO ST/FT-Q Pt 23 1NW245 CN-1569-1.0 C11 2 C ACT Check SA FSO/C-Q CN-NW 23 , CN-1569-1.0 C11 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1NW246 Section 3.2 NW - 4 of 5 Rev. 23 06/29/96
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Unit 1 - Catawba Nuclear Station - inservice Testing Program TEST TEST ' ACT REQ WT REQ wT JUSTtP FOR - TEST PLOW PLOW ASME VALVE ACT CATGRY PAS VALVE TYPE TYPE 30 0 . 1 00 0 . 2 REUEF REQST DEP95UIL ReeMES ALTHWeATTVES REV VALVE IsubeBER OtAGRAM Co0R CLASS t CONTAINMENT PENETRATION VALVE INJECTION WATER SYSTEM (NW) J11 2 C PAS Relief SA -RV 150 PSIG 23 1NW247 CN-1569-1.0. 1NW248 CN-1569-1.0 D11 2 C PAS Relief SA RV 150 PSIG .23 1NW249 CN-1569-1.0 DOS 2 C PAS Relief SA RV 150 PSIG 23' i h NW - 5 of 5 Section 3.2_ 06/29/96 Rev. 23 sw- . , . . , , ,
Unit 1 - Catawba Nuclear Station Inserwce Testing Program TEST' TEST VALVE ACT ACT MQWT MQwT JUSTW FOR TEST FLOW FLOW ASME COOR CLASS CATORY PAS VALVE TYPE TYPE 90 0 .1 90 0 . 2 RELIEF REOST - DEFUWulL REMAfutS ALTUW8ATWES REV
-VALVEseURSER DtAGRAM FIRE PROTECTICN SYSTEM (RF) 1RF3898 CN-1599-2.2 D07 2~ A ACT Gate MO ST-Q PI - 23 1RF392 CN-1599-2.2 F07 2 A/C ACT Check SA FSCWC-Q U CN4tF-01 23 1RF4478 CN-1599-2.2 - CO3 2 A ACT Gate MO. ST-Q Pt 23 ,
1RF448 CN-1599-2.2 E03 2 A/C ACT Check SA FSO/C-Q U CN-RF-01 23 1RF4578 CN-1599-2.2 CO2 2 B ACT Gate MO ST-Q PI 23-i 9 Section 3.2 RF- 1 of 1 Rev.23 06/29/96 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -___ _ . - , . _ _ _ . __ . . _ ._ - _ , _ . _ . ~ . _ _
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\,y Unit 1 - Catawba Nuclear Station Inservice Testog Program TEST -TEST FLOW FLOW ASME VALVE ACT ACT REQ 1dT REQ 1tT . #JSTF FOR . TEST VALVE NUMBER DIAGRAM COOR CLASS CATGRY PAS VALVE TYPE TV'E NO1 NO 2 REUEF REQST DEFERRAL. REMARKS. ALTERNATWES REV NUCLEAR SERVICE WATER SYSTEM (RN) 1RN009 - CN-1574-1.0 E03 3 C ACT Check SA FSO/C-Q 23 1RN011A CN-1574-1.0 E06 3 B ACT Ball MO ST-Q Pl 23-1RN018 CN-1574-1.2 F02 .3 C ACT Check SA FSO/C-Q 23 1RN0208 CN-1574-1.2 E05 3 B ACT Ball MO ST-Q PI 23 1RN028A CN-1574-1.0 E03 3 B ACT Butterfly MO ST-Q Pl ;23 1RNO38B CN-1574-12 F02 3 B ACT Butterfly MO ST-Q PI 23 1RN047A CN-1574-1.1 10 3 3 B ACT Butterfly MO ST-Q Pt 23 1RN0488 CN-1574-1.1 10 5 3 B ACT Butterfly MO ST-Q P1 23 1RN049A CN-1574-1.1 H04 3 B ACT Butterfly MO ST-Q Pl ~23 1RN050B CN-1574-1.1 G04 3 B ACT Butterfly MO ST-Q PI 23 1RN051A CN-1574-1.1 COB 3 B ACT Butterfly MO ST-Q Pt 23 1RN052B CN-1574-1.1 C08 3 B ACT Butterfly MO ST-Q PI 23' 1RN144A CN-1574-2.0 B08 3 B ACT Butterfly MO ST-Q PI 23 '-
1RN148A CN-1574-2.0 L11 3 B ACT Butterfly MO ST-Q Pt 23 1RN225B CN-1574-2.4 BOB 3 B ACT Butterfly MO ST-Q Pt 23 1RN229B CN-1574-2.4 L11 3 B ACT Butterfly MO ST-Q PI ~23 1RN232A CN-1574-2.1 D02 3 B ACT Butterfly MO ST-Q Pl 23 1RN250A CN-1574-2.1 C07 3 B ACT Gate MO ST-Q PI 23 . 1RN291 CN-1574-2.1 K13 3 B ACT Dall AO ST/FT-Q Pi 23 1RN292B CN-1574-2.5 D02 3 B ACT Butterfly MO ST-Q Pt 23 1RN310B CN-1574-2.5 C07 3 8 ACT Gate MO ST-Q PI 23 1RN351 CN-1574-2.5 K13 3 B ACT Ball AO ST/FT-Q Pt 23 1RN404B CN-1574-2.8 GOS 2 B ACT Gate MO ST-Q Pi 23 1RN405 CN-1574-2.8 G03 2 A/C ACT Check SA FSO/C-Q LJ CN-RN-01 23 1RN430 CN-1574-2.2 GO8 2 A/C ACT Check SA FSC-Q U 23 ' 1RN4378 CN-1574-2.8 G12 .2 B ACT Gate MO ST-Q PI CN-RN-02 23 1RN438 CN-1574-2.8 D13 2 A/C ACT Check SA FSO/C-Q U CN-RN-01 23 Section 3.2 RN - 1 of 2 Rev.23 06/29/96
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l - Unit 1 - Catawba Nuclear Stabon - Inservice Testing Program TEST TEST FLOW FLOW ASME VALVE ACT ACT REQWT REQWT JUSTIF FOR TEST VALVE NUMSER DEAGIUus COOR CLASS CATGRY PAS VALVE TYPE TYPE NO1 NO 2 RELIEF REOST DEFERRM REMARKS ALTEfumTfWS REV'
- NUCLEAR SERVICE WATER SYSTEM (RN)
' 1RN484A CN-1574-2.2 G08 2 B ACT Gate MO ST-Q Pi CN-RN-03 23.
1RN485 CN-1574-2.2 G09 2 A/C ACT Check SA FSC-Q LI 23 1RN487B CN-1574-2.2 F08 2 B ACT Gate MO ST-Q Pl CN-RN-03 ,
"- 23 l 1RN846A CN-1574-2.1 J02 3 8 ACT Butterfly MO ST-Q PI 23-1RN847A CN.1574-2.1 J01 3 B 'ACT Butter 9y MO ST-Q PI '23-1RN848B CN-1574-2.5 J02 3 B ACT Butterfly MO ST-Q - Pi : 23-1RN8498 CN-1574-2.5 J01 3 B ACT Butter 9y MO ST-Q Pt 23 1RN854 CN-1574-1.0 F12 3 C ACT Relief SA RV '-0.2 PSIG 23 1RN855 CN 1574-1.0 F03 3 C ACT Relief SA RV -0.2 PSIG -- 23 2
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Unit 1 - Catawba Nuclear Stahon inservice Testing Program TEST - TEST now now AsasE vuvE Ac7 Acr nEo w REow .. wSw coR -- _ TsST CATORY PAS VALVE TYPE TYPE NO.1 REEEFREOST DEFWWWL ******* ' MTWWBA1 WEB IEV ..; VALW IgunASER DIAGWA COOR CLASS 80 0 . 2 MAIN STEAM TO AUX EQUIPMENT (SA)
'1SA002 CN-1593-1.1 G04 2 B ACT Gate AO ST/FT-Q . Pi -23L 1SA003 CN-1593-1.1 G05 2 C ACT Check SA FSOCQ CN-SA-01 23 ' .
1SA005 ~ CN-1593-1.1 H04 2 B ACT Gate AO ST/FT-Q Pl ~ ' 23 1SA006 CN-1593-1.1 ' H05 2 C ACT Check SA FSO/C-Q CN-SA-01 23 - Section 3.2 . SA - 1 of 1 Rev.23 06/29/96
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TEST TEST VALVE ACT ACT REQWT REQWT JUSTIF FOR TEST FLOW FLOW A9aAE DIAGRAIA COOR CLASS CATORY PAS VALVE TYPE TYPE NO.1 NO. 2 RERJEF REQET DEF9 MAL RESAAfuts ALTERNATIVES REV - VALVENutsBER MAIN STEAM (SM) 15M001 CN-1593-1.0 K13 2 B ACT Globe AO ST/FT-Q Pi . CN-SM-01 23
.1SM003 CN-1593-1.0 H13 2 B ACT Globe AO ST/FT-Q Pi CN-SM-01 23 1SM005 CN-1593-1.0 F13 2 B ACT Globe AO ST/FT-Q Pl CN-SM-01 23 CN-1593-1.0 C13 2 B ACT Globe AO ST/FT-Q PI CN-SM-01 23 - >
1SM007 1SM009 CfJ-1593-1.0 J13 2 B ACT Globe AO ST/FT-Q Pi- '23 , 1SM010 CN-1593-1.0 G13 2 B ACT Globe AO ST/FT-Q Pl 23 1SM011 CN-1593-1.0 E13 2 B ACT Globe AO ST/FT-Q Pi - 23 1SM012 CN-1593-1.0 B13 7 B ACT Globe AO ST/FT-Q PI 23 I 1 SM - 1 of 1 Section 3.2 Rev.23 06/29/96
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O O O Unit 1 - Catawba Nuclear Station Inservice Teshng Program v=ve DES T EEUr era ecR rssr - now now Asw Act Act Remus MTERNATMs Atv CATGRY PAS VMVE TYPE TYPE No.1 NO. 2 REUU REOST DUERR E - vuve NumetR DIAGAM COOR CLASS MAIN STEAM TO ATMOSPHERE (SV) 2 B ACT Globe AO ST/FT-Q PI 23 1SV001 CN-1593-1.0 L12 2 C ACT Relief SA RV 1175 PSIG 23 1SV002 CN-1593-1.0 K04 2 C ACT Relief SA RV ' 1190 PSIG 23 1SV003 CN-1593-1.0 K06 K07 2 C ACT Relief SA RV 1205 PSIG 23 1SV004 CN-1593-1.0 K08 2 C ACT Relief SA RV 1220 PSIG 23 1SV005 CN-1593-1.0 K10 2 C ACT Relief SA RV 1230 PSIG 23 1SV006 CN-1593-1.0 2 B ACT Globe AO ST/FT-Q PI 23 1SV007 CN-1593-1.0 11 2 2 C ACT Relief SA RV 1175 PSIG . 23 1SV008 CN-1593-1.0 104 2 C ACT Relief AO RV 1190 PSIG 23 1SV009 CN-1593-1.0 10 6 CN-1593-1.0 2 C ACT Relief MO RV 1205 PSIG 23 1SV010 10 7 CN-1593-1.0 108 2 C ACT Relief AO RV 1220 PSIG 23 1SV011 2 C ACT Relief AO RV 1230 PSIG 23 , 1SV012 CN-1593-1.0 11 0 CN-1593-1.0 F12 2 B ACT Globe AO ST/FT-Q PI 23 1SV013 CN-1593-1.0 F04 2 C ACT Relief SA RV 1175 PSIG 23 1SV014 CN-1593-1.0 F06 2 C ACT Relief SA RV 1190 PSIG 23 1SV015 CN-1593-1.0 F07 2 C ACT Relief SA RV 1205 PSIG 23 1SV016 CN-1593-1.0 F08 2 C ACT Relief SA RV 1220 PSIG 23 1SV017 CN-1593-1.0 F10 2 C ACT Relief SA RV 1230 PSIG 23 1SV018 1SV019 CN-1593-1.0 D12 2 8 ACT Globe AO ST/FT-Q Pl 23-1SV020 CN-1593-1.0 C04 2 C ACT Relief SA RV 1175 PSIG 23 1SV021 CN-1593-1.0 C06 2 C ACT Relief SA RV 1190 PSIG 23 1SV022 CN-1593-1.0 C07 2 C ACT Relief SA RV 1205 PSIG 23 1SV023 CN-1593-1.0 C08 2 C ACT Relief SA RV 1220 PSIG 23 1SV024 CN-1593-1.0 C10 2 C ACT Relief SA RV 1230 PSIG ' 23 1SV025B CN-1593-1.0 K11 2 B ACT Gate MO ST-Q PI 23 1SV0268 CN-1593-1.0 11 1 2 B ACT Gate MO ST-Q PI 23 CN-1593-1.0 C11 2 B ACT Gate MO ST-Q PI 23 1SV027A CN-1593-1.0 F11 2 B ACT Gate MO ST-Q Pl 23 1SV028A Section 3.2 SV - 1 of 1 Rev. 23 06/29/96
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Unit 1 - Catawba Nuclear Station InservKe Testing Program TEST TEST FLOW - FLOW ash 8E VALVE ACT ACT REQ WT REQwT JusTIF FOR TEST VALVEsUe8SER DIAGRAAA COOR CLASS CATGRY PAS VALVE TYPE TYPE $80.1 NO.2 REUEF RE.QST DEFEpWtAL REteAAKS ALTERNATtJES REV BREATHING AIR SYSTEM,(VB) 1VB0838 CN-1605-3.2 10 7 2 A ACT Diaphram MO ST-Q U/Pl 23 1VB085 CN-1605-3.2 H07 2- A/C ACT Check SA FSO/C-Q U CN VB-01 23 l l Section 3.2 VB - 1 of 1 Rev.23 06/29/96 ;
4 Unit 1 - Catawba Nuclear Station inservice Teshng Program TEST. TEST ROW - FLOW Asatt VMWE Act Act - nEQtAT ReQwT JusTarFOR - TEST-v=ve nunseen cuenans coon etAss cATany -ens vuve Type Type no.i no. 2 - neuerneQsf oefunna manuwets - misunniwes nev DIESEL GENERATOR ENGINE STARTING AIR (VG)
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'1VG006 CN-1609-4.G 11 3 3 C ACT Check SA' FSC-Q 23
- 1VG007 CN-1609-4.0 J02 3 C ACT Check SA FSC-Q 23 -
- 1VG006 CN-1609-4.0 J13 3 C ACT Check SA- FSC-Q 23 1VG015 _ CN-160lM.0 G02 3 C ACT Check SA FSO/C-Q CN-VG-01 .23. 7 1VG016 CN-160lk4.0 G13 3 C ACT - Check SA FSO/C-Q CN-VG-01 23-1VG025 CN-1609-4.0 DOS 3. 8 ACT Gate SO ST-Q Pi CN-VG-02 - 1VG026 CN-160Ek4.0 D10 3 B ACT Gate SO ST-Q Pi CN-VG 02 23 1VG027 - CN-1609-4.0 C05 3 B ACT Gate SO ST-Q Pl CN-VG412 23 '[
1VGO28 CN-1609-4.0 .C10 3 B ACT Gate SO ST-Q ' Pl CN-VG-02 - '3 1VG029 CN-1609-4.0 DO6 3 C ACT Check SA - FSOC Q CN-VG41 -23 i 1VG030 CN-1609-4.0 D10 3 C ACT Check SA FSOCQ CN-VG-C1 ' 1VG031 CN-1609-4.0 C05 3 C ACT Check SA FSOCQ CN-VG 01 23 1VG032 CN-160lM.0 C10 3 C ACT Check SA FSO/C-Q CN-VG-01 : 23 1VG049 CN-160lM.1 10 2 3 C ACT Check SA FSC-Q 23 1VG050 - CN-160EM.1 11 3 3 C ACT Check SA FSC-Q 23 1VG051 CN-160lM.1 10 2 3 C ACT Check SA FSC-Q 23 4 1VG052 CN-160lM.1 11 3 3 C ACT Check SA . FSC-Q 23. 1VG059 CN-160lM.1 F02 3 C ACT Check SA FSO/C-Q CN-VG-01 23. f 1VG060 CN-160lM.1 F13 3 C ACT Check SA FSOCQ CN-VG-01 23 l 1VG069 CN-160lM.1 005 3 B ACT Gate SO ST-Q P1 CN-VG-02 23 1VG070 CN-1609-4.1 D10 3 B ACT Gate SO ST-Q Pl CN-VGLO2 23 l 1VG071 CN-160lk4.1 C05 3 B ACT Gate SO ST-Q Pi CN-VG-02 _23' 1VG072 CN-1609-4.1 C10 3 B ACT Gate 30 ST-Q Pi CN-VG-02 23 1VG073 CN-160iM.1 DOS 3 C ACT Check SA FSOCQ CN-VG-01 23 ' ( 1VG074 CN-1609-4.1 D10 3 C ACT Check SA FSOCQ CN-VG-01 23 l 1VG075 CN-1609-4.1 COS 3 C ACT Check SA FSOCQ CN-VG-01 :23 1VG076 CN-1609-4.1 C10 3 C ACT Check SA FSOKXI CN-VG-01
-23 Section 3.2 . VG - 1 of 2 Rev.23 06/29/96
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Inservice Testing Program TEST TEST ' VALVE ACT ACT REQMT REQ MT JUSTIF FOR TEST FLOW FLOW ASME COOR CLASS CATORY PAS VALVE TYPE TYPE B00.1 - 8e0. 2 RELIEF REOST DErsWML REMApats ALTsusATivEs REV VALVE esuMSER DLAGRAM INSTRUMENT AIR SYSTEM (VI) CN-1605-1.4 K06 2 A ACT Diaphram MO ST-Q LitPI CN-VI-02 23-1V10778 . CN-1605-1.4 H09 2 A/C ACT Check SA FSO/C-Q U- CN-VI-01 23 1V1079 CN-1605-1.4 H06 2 A ACT Globe MO ST-Q Ll/PI 23 1Vl312A 1Vl367 CN-1605-1.14 E11 - C ACT Check SA FSO/C-Q CN-VI-03 23' CN-1605-1.14 E12 C ACT Check SA FSO/C-Q CN-VI-03 ' 23 ' 1Vl368 -
' CN-1605-1.14 F10 C ACT Check SA FSO-Q CN-VI-04 23 1V1369 -
1Vl370 CN-1605-1.14 F13 - C ACT Check SA FSO-Q CN-VI-04 23 b i Section 3.2 VI-1of1 Rev. 23 06/29/96
~ O O O Unit 1 - Catawba Nuclear Stahon Inservice Testing Program TEST TEST FLOW PLOW AShtE VALVE ACT ACT REQ wT REQ wT JUSTIF F0ft TEST DIAGRAte COOR CLASS CATGRY PAS VALVE TYPE TYPE ' 3e0.1 %.2 REDEF REQST DEFEfutAL REktefuls - ALTWW6ATWE5 REV ' VALVESMAASER
' CONTAINMENT PURGE VENTILATION SYSTEM (VP) 1VP001B . CN-1576-1.0 10 5 2 A PAS Butterfly AO LJIPI 23 -
1VP002A CN-1576-1.0 10 6 2 A PAS Butterity AO LJtPI 23 . 1VP0038 CN-1576-1.0 H05 2 A PAS Butterity AO LPPI 23 1VP004A CN-1576-1.0 H06 2 A PAS Butterfly AO LJ/PI 23 1VP0068 CN-1576-1.0 G05 2 A PAS Butterfly AO LJIPI 23 1VP007A CN-1576-1.0 G06 2 A PAS Butterfly AO LJIPl 23 1VP0088 ' CN-1576-1.0 F05 2 A PAS Butterfly AO LJIPl 23 1VP009A ' CN-1576-1.0 F06 2 A PAS Butterfly AO LJ/PI 23 1VP010A CN-1576-1.0 10 9 2 A PAS Butterfly AO LJtPI 23 1VP011B CN-1576-1.0 11 0 2 A PAS Butterfly AO LJIPI 23 1VP012A CN-1576-1.0 H09 2 A PAS Butterfly AO LitPl 23 1VP0138 CN-1576-1.0 H10 2 A PAS Butterfly AO LJIPI 23 1VP015A CN-1576-1.0 F09 2 A PAS Butterfly AO LJ/PI 23 1VP0168 CN-1576-1.0 F10 2 A PAS Butterfly AO LJ/Pl 23 1VP017A CN-1576-1.0 E09 2 A PAS Butterfly AO LJ/PI 23 1VP0188 CN-1576-1.0 E10 2 A PAS Butterfly AO LJIPI 23 1VP019A CN-1576-1.0 E06 2 A PAS Butterfly AO LJIPI 23 1VP0208 CN-1576-1.0 EOS 2 A PAS Butterfly AO LJ/PI 23 t l l Section 3.2 VP- 1 of 1 Rev.23 06/29/96
Q ) rN N/ . Unit 1 - Catawba Nuclear Station Inservice Testing Program TEST. TEST ACT ACT MOWT MowT . JUSTIF FOR TEST , FLOW FLOW A9aAE VALVE CATGRY PAS VALVE TYPE TYPE NO.1 NO. 2 ftEUEF MOST DEFENIAL ResAfuls ALT 94eATIVES . MV
. VALVE NURASER OtAGRABA COOR CLASS CONTAINMENT AIR RELEASE & ADDITION SYSTEM (VQ) 2 A ACT Diaphram MO ST-Q Ll/PI 23 1VQ 02A CN-1585-1.0 10 2 G02 2- A ACT Gate MO ST-Q LJ/Pt 23 1VQ0038 CN-1585-1.0 2 A ACT Gate MO ST-Q t.J/PI 23 1VQO158 CN-1585-1.0 11 2 CN-1585-1.0 J12 2 A ACT Diaphram MO ST-Q LJ/PI 23 1VQO16A
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'I TEST TEST ACT ACT MQWT REQWT JUSTIF FOR TEST Flow FLOW - ASME VALVE peo.1 seo. 2 REUEF MQST DEFERRAL REMARKS ALTEpusATIVES - REV VALVE peUMSSR 06AGRAM COOR CLASS .CATGRY PAS VALVE TYPE TYPE CONT. AIR RET. & HYDROGEN SKIMMER SYSTEM (VX)
G03 2 B ACT Butterfly MO ST-Q PI 23 1VX001A CN-1557-1.0 G14 2 B ACT Butterfly MO ST-Q Pt 23 ., 1VX0028 CN-15571.0 i i Section 3.2 VX - 1 of 1 Rev.23 06/29/96
~c Unit 1 - Catawba Nuclear Station Inservice Testing Program TEST TEST FLOW FLOW ASRAE VALVE ACT ACT REO MT MQwT JUSTnFFOR TEST vavE Muheem otAaRar .COOR CLASE CATORY PAS V MVE TYPE TWE #0.1 MO. 2 . REDEFREOST OEFmRE RBWES RTUusADWS REV '
CONTAINMENT HYDROGEN SAMPLE & PURGE SYSTEM (W) 1WO158 CN-1559-1.0 F07 2 A PAS - Gate MO- U Pt 23 1WO16 CN-1559-1.0 D07 2 AIC ACT Check SA FSO/C-Q U CN-W41 23 1WO17A - CN-1559-1.0 D04 2 A PAS Gate MO U PI 23 , 1WO188 CN-1559-1.0 G04 2 A PAS Gate - MO U Pt 23 l' t Section 3.2 VY- 1 of 1 l l Rev. 23 06/29/96 l-
4 Unit 1 - Catawba Nuclear Station Inservice Testing Program
.y TEST TEST.
Ashet V RVE 'ACT ACT - REQwT REQWT JUSTIF FOR . TEST ROW FLOW PAS VALVE TYPt TYPE 90 0 . 2 REUEF REQST OEF94%AL REn4 ARKS ALTERNATIVES , REV . 4 VALVE BeURAGER OWh0RAsd COOR CLASS CATORY 10 0 .1 EQUIPMENT DECONTAINMENT SYSTEM (WE) 1WE020 CN-1568-1.0 E11- 2 A PAS Globe MA U 23
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R Q ,- b U ()y _ Unit 1 - Catawba Nuclear Station Inservice Testing Frogram TEST TEST ASME VALVE ACT ACT REQ WT REQ MT ' JUSTIF FOR TEST FLOW FLOW PAS VALVE TYPE TYPE - MO.1 NO. 2 REUEF REQST DEPEMAL REMARKS ALTgquATIVES REV VALVE NUMBER DIAGRAM COOR CLASS CATORY LIQUID WASTE RECYCLE SYSTEM (WL) 1WL321' CN-1565-2.4 H06 2 NC ACT Check SA FSC-Q U 23 1WL450A CN-1565-2.0 10 4 2- A ACT Globe MO ST-Q U/PI 23-1WL451B CN-1565-2.0 J04 2 A ACT Globe MO ST-Q U/PI 23 1WL805A CN-1565-2.0 H08 2 A ACT Gate MO ST-Q U/PI 23 1WLS06 CN-1565-2.0 10 8 2 NC ACT Check SA FSC-Q U 23 1WL807B CN-1565-2.0 J08 2 A ACT Gate MO ST-Q U/PI 23 1WL825A CN-1565-2.4 H07 2 A ACT Gate MO ST-Q U/PI 23 1WL827B CN-1565-2.4 J07 2 A ACT Gate MO ST-Q U/PI 23-1WL830 CN-1565-2.2 H04 3 C ACT Check SA FSO/C-Q 23 1WL832 CN-1565-2.2 HOS 3 C ACT Check SA FSO/C-Q 23 1WL867A CN-1565-2.1 10 7 2 A ACT Gate MO ST-Q U/PI 23 1WL868 CN-1565-2.1 106 2 AIC ACT Check SA FSC-Q U 23 1WL8698 CN-1565-2.1 H07 2 A ACT Gate MO ST-Q LJ/PI 23 ; 1WLA022 CN-1565-2.6 K10 2 NC ACT Check SA FSC-Q LJ 23 i Section 3.2 WL - 1 of 1 Rev. 23 06/29/96
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COOR CLASS CATORY PAS VALVE TWE TYPE iso.1 peo. 2 REuff MOST DEPURA REheAfuS ALTsueATWES REV VALVE NUtssER DIAGRAfd MAKEUP DEMiNERAI 17FR WATER SYSTEM (YM) 1YM1198 CN-1601-3.1 E06 2 A ACT Globe MO ST-Q U/PI 23 1YM121 CN-1601-3.1 E04 2 A/C ACT Check SA FSCWC-Q U CN-YM-01 23 i i i I
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Section 3.2 YM - 1 of 1 .; Rev. 23 06/29/96
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! CATAWBA NUCLEAR STATION l' Unit 2 1 l l J l i-
- ASME Inservice Testing Program l
O
m UNIT 2 - CATAWBA NUCLEAR STATION Pump inservice Testing Program Code Inlet . Differennel Row-Ptoup D. humber r__,_. Class Pump Type Flow Diagram Speed Pressure Ptoseure Vaweden Rees Rehof Regumet Resnorks Rev 2CAPUOOO1 Motor Driven 3 Centrifugal CN-2592-1.0 NR Q .O Q Q CN-SRP-CA-01 NONE 23 Auxiliary Feedweter i Pump 2A 2CAPUOOO2 Motor Driven 3 Centrifugel CN-2592-1.0 NR Q Q Q Q CN-SRP-CA-01 NONE 23 Auxiliary Feedwater Pump 28 2CAPUOOO3 Turbine Driven 3 Centrifugal CN-2592-1.0 Q Q Q Q Q NONE 23 Auxiliary Feedwater Pump #2 2KCPUOOO1 Component Cooling 3 Centrifugal CN-2573-1.0 NR Q Q Q Q NONE 23 Water Pump 2A1 2KCPUOOO2 Component Cooling 3 Centrifugal CN-2573-1.0 NR Q Q Q Q NONE 23 Weter Pump 2A2 1 2KCPUOOO3 Component Cooling 3 Centrifugal CN-2573-1.0 NR Q Q Q Q NONE 23 Weter Pump 281 . t 2KCPUOOO4 Component Cooling 3 Centrifugal CN-2573-1.0 NR O Q Q Q NONE 23 Water Pump 2B2 2NDPUOOO1 fiesidual Heat 2 Vertical Line CN ,2561-1.0 NR Q Q Q Q NONE 23 Removal Pump 2A Shaft Centrifugal e Rev.23 SECTION 4.1 06/29/96 1 OF 2
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l' UNIT 2 - CATAWBA NUCLEAR STATION Pump inservice Testing Program l' l l coe. Inlet Dwswunnel Flow Pump D. Fewnber Onee Pung Type Flow Diserene Speed Ptooews Ptooewe Veweden Rees Romet Roguest RomeAs Row P: ._ 2NOPUOOO2 Resedual Heat 2 Vertical Line CN-2561-1.1 NR- Q Q Q Q NONE 23 Removal Pump 28 Shaft Centrifugal 2NIPUOOO9 Safety injection 2 Centrifugal CN-2562-1.2 NR Q Q Q Q NONE 23 Purnp 2A
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2NIPUOO10 Safety injection 2 Centrifugal CN-2562-1.2 NR O Q Q Q NONE 23 Purnp 28 2NSPUOOO1 Conteinment Sprey 2 Vertical Line CN-2563-1.0 NR Q Q Q Q NONE 23 Pump 2A Shaft Centrifugal i 2NSPUOOO2 Containment Spray 2 Vertical Line CN-2563-1.0 NR Q Q Q Q NONE 23 Pump 2B Shaft ! Centrifugel 2NVPUOO15 Centrifugal Charging 2 Centrifugal CN-2554-2.0 NR Q Q Q Q NONE 23 Pump 2A - t 2NVPUOO16 Centrifugal Charging 2 Centrifugal CN-2554-1.7 NR Q. Q Q Q NONE 23 Pump 2B 2RNPUOOO2 Nucieer Service 3 Vertical Line CN-2574-1.0 NR Q Q Q Q NONE 23 Water Pump 2A Shaft Centrifugal 2RNPUOOO4. Nuclear Service 3 Vertical Line CN-2574-1.2 NR Q Q Q Q NONE 23 Water Pump 2B Shaft [ Centrifugal t Rev.23 SECTION 4.1 t 06/29/96 2OF2
[ Q. N _ Unit 2- Catawba Nuclear Station Inservice Testing Program TEST TEST. FLOW FLOW ASME VALVE ACT ACT REQMT REQ MT JUSTtF FOR TEST VALVE NUMBER ORAGRAM COOR CLASS CATORY PAS VAtVE TYPE TYPE NO.1 ' NO. 2 RELIEF REOST DEF9 MAL REMMULS ALTSWsATIVES REV - STEAM GENERATOR BLOWDOWN RECYCLE (BB) . 2BB008A CN-2580-1.0 JOS 2 B ACT Gate MO ST-Q Pi - 23 2880108 ' CN-2580-1.0 J06 2- B ACT . Gate MO ST-Q Pl 23 2BB019A CN-2580-1.0 DOS' 2 B ACT Gate MO ST-Q PI 23' 2BB021B CN-2580-1.0 DOS 2 B ACT Gate MO ST-Q PI 23-2BB056A CN-2580-1.0 H05 2 B ACT Gate MO ST-Q Pl 23 288057B CN-2580-1.0 H06 2 B ACT Gate MO ST-Q Pl - 23 2BB060A CN-2580-1.0 F05 2 B ACT Gate MO ST-Q PI 23 288061B CN-2580-1.0 F06 2 B ACT Gate MO ST-Q PI 23-2BB147B CN-2580-1.0 K06 2 B ACT Globe MO ST-Q PI 23 2BB1488 CN-2580-1.0 10 6 2 B ACT Globe MO ST-Q PI 23 2BB1498 CN-2580-1.0 G06 2 B ACT Globe MO ST-Q PI 23 2881508 CN-2580-1.0 E06 2 B ACT Globe MO ST-Q Pt 23 5-Section 4.2 BB - 1 of 1 06/29/96 Rev. 23
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r, i , . Unit 2 - Catawba Nuclear Station ' inservice Testeg Program TEST' TEST vave sounseen O E E cNE E vuve rm E "SY s sooY neue meosr "E" nemus areEnves nev ., AUXIUARY FEEDWATER SYSTEM (CA) 2CA006 CN-2592-1.0 DOS 3 C ACT Check SA FSOC-Q CN-CA-03 23' 2CA010 CN-2592-1.0 DOS 3 C ACT Check SA FSO/C-Q CN-CA-03 23 2CA012 CN-2592-1.0 D01 3 C ACT Check SA FSO/C-Q CN-CA-03 23 2CA015A CN-2592-1.0 D02 3 B ACT Gate MO ST-Q Pt 23 2CA0188 CN-2592-1.0 D06 3 B ACT Gate MO ST-Q Pi- 23 2CA020 CN-2592-1.0 11 1 3 C ACT 3-Way SA FS ~ 23 2CA023 - CN-2592-1.0 J10 3 C ACT Check SA FSOC-Q 23 2CA027 CN-2592-1.0 10 4 3 C ACT 3-Way SA FS' 23 2CA028 CN-2592-1.0 J03 3 C ACT Check SA FSO/C-Q 23 2CA032 CN-2592-1.0 10 8 3 C ACT 3-Way SA FS 23
'2CA033 CN-2592-1.0 J07 3 C ACT Check SA FSOJC-Q 23 2CA036 CN-2592-1.1 C12 3 B ACT Globe AO ST/FT-Q Pt 23 ,
2CA037 CN-2592-1.1 G12 2 C ACT Check SA FSO/C-Q CN-CA-01 23 2CA038A CN-2592-1.1 H12 2 B ACT Gate MO ST-Q PI 23 2CA040 CN-2592-1.1 J12 3 B ACT Globe AO ST/FT-Q PI 23 2CA041 CN-2592-1.1 11 2 2 C ACT Check SA FSO/C-Q CN-CA-01 23 2CA0428 - CN-2592-1.1 11 2 2 B ACT Gate MO ST-Q - PI 23 2CA044 CN-2592-1.1 JO9 3 B ACT Globe AO ST/FT-Q PI 23 , 2CA045 CN-2592-1.1 109 2 C ACT Check SA FSO/C-Q CN-CA-01 23 2CA046B CN-2592-1.1 10 9 2 B ACT Gate MO ST-Q Pt 23 2CA048 CN-2592-1.1 C09 3 B ACT Globe AO. ST/FT-Q PI 23 2CA049 CN-2592-1.1 G09 2 C ACT Check SA FSO/C-Q CN-CA-01 23' 2CA050A CN-2592-1.1 H09 2 B ACT Gate MO ST-Q Pl 23 2CA052 CN-2592-1.1 C06 3 B ACT Globe AO ST/FT-Q PI- 23 , 2CA053 CN-2592-1.1 G09 2 C ACT Check SA FSO/C-Q CN-CA-01 23~ 2CA054B CN-2592-1.1 H06 2 B ACT Gate MO ST-Q Pt 23 - 2CA056 CN-2592-1.1 J06 3 B ACT Globe AO ST/FT-Q Pl 23 2CA057 CN-2592-1.1 106 2 C ACT Check SA FSO/C-Q CN-CA-01 23 Section 4.2 CA - 1 of 2 Rev.23 06/29/96 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ . - _. _ _ _ ___________m_._ _ _ _ - . _ - . __ ___m. _ _ _
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O O O Unit 2- Catawba Nuclear Station Inservice Testing Program TEST TEST Ashot VALVE ACT ACT RtQMT REQwT JUST1F FOR TEST FLOW FLOW DIAORAM COOR CLASS CATGRY PAS VALVE TYPE TYPE peo.1 Iso. 2 REL1EF REQST DE8ERRAL ROAARKS ALTEmeATIVES REV VALVE NUhesER AUXILIARY FEEDWATER SYSTEM (CA) 2CA058A CN-2592-1.1 10 6 - 2 B ACT Gate MO ST-Q Pt 23 . 2CA060 CN-2592-1.1 J03 3 B ACT Globe AO ST/FT-Q Pt 23 2CA061 CN-2592-1.1 10 3 2 C ACT Check SA FSO/C-Q CN-CA-01 23-2CA062A CN-2592-1.1 10 3 2 B ACT Gate MO ST-Q . Pl - 23 CN-2592-1.1 CO3 3 B ACT Globe AO ST/FT-Q Pt 23 2CA064 2CA065 CN-2592-1.1 G03 2 C ACT Check SA FSO/C-Q CN-CA-01 23 2CA0668 CN-2592-1.1 H03 2 B ACT Gate MO ST-Q PI 23 2CA0858 CN-2592-1.0 D07 3 B ACT Gate MO ST-Q Pt 23 2CA116A CN-2592-1.0 D08 3 B ACT Gate MO ST-Q PI 23 2CA149 CN-2592-1.1 10 1 2 B ACT Gate AO ST/FT-Q Pl CN-CA-05 23 2CA150 CN-2592-1.1 10 5 2 B ACT Gate AO ST/FT-Q Pl CN-CA-05 23 2CA151 CN-2592-1.1 10 8 2 B ACT Gate AO ST/FT-Q Pi CN-CA-05 23 2CA152 CN-2592-1.1 111 2 B ACT Gate AO ST/FT-Q Pi CN-CA-05 23 2CA171 CN-2592-1.0 C06 3 C ACT Check SA FSO/C-Q CN-CA-02 23 2CA172 CN-2592-1.0 C08 3 C ACT Check SA FSO/C-Q CN-CA-02 23 2CA173 CN-2592-1.0 E08 3 C ACT Check SA FSO/C-Q CN-CA-04 23 2CA185 CN-2592-1.1 E01 2 B ACT Gate AO ST/FT-Q Pt 23 2CA186 CN-2592-1.1 EOS 2 B ACT Gate AO ST/FT-Q Pl 23 2CA187 CN-2592-1.1 E08 2 B ACT Gate AO ST/FT-Q PI 23 2CA188 CN-2592-1.1 E11 2 B ACT Gate AO ST/FT-Q Pl 23 Section 4.2 CA - 2 of 2 Rev. 23 06/29/96
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Unit 2-Catawba Nuclear Stahon .)l - inservice Teshng Program _ t TEST TEST l FLOW FLOW . ASRAE . VALVE ACT ACT REQtfT - REQtsi . ^ JUSTF FOR ' TEST-VALVEpaesmFR DinGftAss COOR CLASS CATGstY PAS VALVE TYPE TYPE. .NO1: - NO 2 IEELt 5 REOST - DEFEfutAL REtapflKS ' ALTEfteATlWE5 REV-I 9 9 . FEEDWATER SYSTEM (CF) -!
'2CF031 . CN-2591-1.1 G13 2 C ACT Check SA FSC-Q ,
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.2CF033 : CN-2591-1.1 ' F13 2 B ACT Gate HO< ST/FT-Q - Pi - . CN-CF-01 ~23 j l l2CF040- . CN-2591-1.1 G09 2 C ACT Check SA -- FSC-Q - 23? ]
2CF042 CN-2591-1.1 F09 2 B ACT Gate HO ST/FT-Q ' Pi - CN-CF-01 23 1 2CF049 'CN-2591-1.1 G06 2 C ACT Check SA FSC-Q 23 , i 2CF051 CN-2591-1.1 F06 2 B ACT Gate HO ST/FT-Q Pl CN-CF-01 23' l 2CF058 CN-2591-1.1 ' G03 2 C ACT Check SA FSC-Q . 23 l !. 2CF080 CN-2591-1.1 F03 2 B ACT Gate HO ST/FT-Q Pl CN-CF-01 23' l 2CF087 CN-2591-1.1 F02 2 B ACT Gate AO ST/FT-Q Pi- 23 ' -i 2CF088 CN-2591-1.1 F06 2 B ACT . Gate - AO ST/FT-Q Pi 23 ' ! i, 2CF089 CN-2591-1.1 F09 2 B ACT Gale AO ST/FT-Q Pl .23 2CF090 CN-2591-1.1 - F13 2 B ACT Gate AO ST/FT-Q PI 23 2CF166- CN-2591-1.1 G13 2 C ACT Check SA FS-Q - 23 i
.2CF167- CN-2591-1.1 - G09 2 C ACT Check -SA- FS-Q 23 r
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I 2CF168 CN-2591-1.1 G06 2 C ACT Check SA FS-Q - ' 23 - 2CF169- CN-2591-1.1 G02 2 C ACT Check SA FS-Q 23 d i 4 i 4 l I i Section 4.2 CF - 1 of 1 - Rev. 23 06/29/96 l i , + ____ ___________m__.____ _.- w _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ , . - . . * , ..- _ . - . _o.e _ _ -__ __ _ __ _ . _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ ___
Unit 2- Catawba Nuclear Station Inservice Testing Program TEST TEST PLOW FLOW ASME VALW ACT ACT REQ WT REQ WT .JUSDFPOR TEST, VALVE stuMSEA DIAGRAM COOR CLASE CATORY PAS VALVE TYPE TYPE Iso.1 Iso. 2 RELIEF REQsf DEPtemAL REMAfKs ALTERenATIVEs : REV - DOESEL GENERATOR ENGINE FUEL OIL SYSTEM (FD) 2FD022 CN-2609-3.0 J13 3 B ACT Globe SO STAT-Q 23 2FD029 CN-2609-3.0 F05 3 C ACT Check SA FSCWC-Q 23
'2FD034 CN-2609-3.0 - H13- 3 C ACT Relief SA RV 40 PSIG 23 -
2FD062 CN-2609-3.1 J12 3 B ACT Globe SO ST/FT-Q . 23 2FD069 CN-2609-3.1 F0E 3 C ACT Check SA FSO/C-Q 23 2FD074 CN-2609-3.1 H13 .3 C ACT Relief SA RV 40 PSIG 23-Section 4.2 FD- 1 of 1 Rev.23 06/29/96
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O O O Unit 2 - Catawba Nur' wr Station Inservice Testing Program TEST' TEST FLOW ASME VALVE ACT ACT REQ WT REQ WT JUSTIF FOR TEST FLOW DIAGRAM COOR CLASS CATGRY PAS VALVE TYPE TYPE NO.1 NO,2 RELIEF REOST . OEFEMAL REMARKS ALTERNATIVES REV -
~. VALVE NUMSER REFUEUNG WATER SYSTEM (FW) 2FWOO1A CN-2571-1.0 J13 2 B ACT Gate MO ST-Q Pt 23 2FWOO4 CN-2571-1.0 LO7 2 A PAS Gate MA U 23 -
2FWOOS CN-2571-1.0 LOS 2 A/C PAS Check SA U 23-2FWO11 CN-2571-1.0 J04 2 A ACT Plug MA U- 23. 2FWO13 CN-2571-1.0 JOS 2 A ACT Plug MA U_ 23 2FWO27A CN-2571-1.0 F03 2 B ACT Gate MO ST-Q Pl 23 2FWO28 CN-2571-1.0 F02 2 C ACT Check SA FSO/C-Q CN-FW-01 23-2FWO32B CN-2571-1.0 J13 2 B ACT Gate MO ST-Q Pl 23 2FWO33A CN-2571-1.0 B08 2 B ACT Globe MO ST-Q Pt 23 2FWO498 CN-2571-1.0 B08 2 B ACT Globe MO ST-Q . Pt 23 , 2FWOS2 CN-2571-1.0 E10 - C ACT Check SA FSO-Q 23 2FWO558 CN-2571-1.0 H03 2 B ACT Gate MO ST-Q Pt 23 2FWO56 CN-2571-1.0 H02 2 C ACT Check SA FSO/C-Q CN-FW-01 23 l Section 4.2 FW - 1 of 1 Rev.23 06/29/96
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O O Unit 2- Catawba Nuclear Station inservice Testi.g Program TEST TEST VALVE ACT ACT REQWT REQwT JUSTIF FOR TEST FLOW FLOW ASME COOR CLASS CATGRY PAS VALVE TYPE TYPE 90 0 .1 00 0 . 2 REUEF REOST DEFENIAI. REMARKS' ALTErmATNES REV VALVE seuMBER DAGRAM INSTRUMENT - AIR LOCK SYSTEM (IA) CN-2499-IA1.01 2 NC ACT Check SA FSC-Q U CN-IA-01 23 2tACV5340 CN-2499-IA1.01 2 NC ACT Check SA FSC-Q U CN-IA-01 23 2tACV5350 CN-24941A1.01 2 NC ACT Check SA FSC-Q U CN-IA-01 23 21ACV5360 2tACV5370 CN-2499-IA1.01 2 NC ACT Check SA FSC-Q U CN-IA-01 23 CN-2499-IA1.01 2 NC ACT Check SA FSC-Q U CN-IA-01 23 2iACV5380 2iACV5390 CN-2499-IA1.01 2 NC ACT Check SA FSC-Q U - CN-IA-01 23 21ASV5080 CN-2499-IA1.01 2 A ACT Globe SO ST/FT-Q U/PI 23 2tASV5160 CN-2499-IA1.01 2 A ACT Globe SO- ST/FT-Q U/Pt 23 2tASV5400 CN-2499-IA1.01 2 A ACT Globe SO ST/FT-Q U/PI 23 -- 2tASV5410 CN-2499-IA1.01 2 A ACT Globe SO ST/FT-Q U/PI 23 , L
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, Section 4.2 IA - 1 of 1 Rev. 23 06/29/96 _ - - - - - _ - - _ . _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . - _ _ _ ______ _ - - - - _ _ - - _ _ _ _ _ _ . - -_._ --. ._ - _ _ _ ~ _ - . - _ - . -
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i Unit 2- Catawba Nuclear Station ~
- Inse<vice Testing Program ,
TEST- TEST Asset VALVE ACT ACT REO MT REOWT JusTIF FOR ' TEST . l Flow ' Plow ALTggsAftVEB 1 REV T PAS- VALVE TYPE TYPE eso.1 too. 2 REUEF REOST - DEPEIutAL ReseARKs vmLVE esuessen DameRAas Coom class CATORY f COMPONENT COOUNG (MC) B ACT Butterfly MO ST-Q Pi -23 1
- 2KC001A- CN-2573-1.0 C06 3 Butterfly - MO- ST-Q Pi . 23; .t 2KC002B . CN-2573-1.0 C09 3 B ACT ACT Gate MO ST-Q Pi - 23 .
2KC003A CN-2573-1.0 - C06 3 B 3 C ACT Check SA- FSOIC-Q ' 23
. 2KC005 CN-2573-1.0 - E04 -
E04 3 C ACT Check SA FSOdC-Q 23 2KC006 . CN-2573-1.0 3 C ACT Check SA FSOdC-Q 23 .i 2KC011 CN-2573-1.0 E11 CN-2573-1.0 E11 3 C ACT Check SA FSOdC-Q 23'
..2KC014 C09 3 B ACT Gate -- MO ST-Q PI 23 .
2KC018B- CN-2573-1.0 H04 2 A/C ACT Check SA FSC4 U 23J 2KC047 CN-2573-1.5 K07 3 B ACT Gate MO ST-Q Pt "23 2KC050A CN-2573-1.0 K08 3 B ACT Gate MO ST-Q Pi . 23 2KC053B CN-2573-1.0 E03 3 B ACT Butterfly MO ST-Q Pl 23 - ! 2KC056A CN-2573-2.0 J03 3 B ACT Globe AO ST/FT-Q PI' 23 f 2KC057A CN-2573-2.0 23 I 2KC081B CN-2573-2.1 E03 3 B ACT Butte 1ty MO ST-Q Pt J03 3 B ACT Globe AO ST/FT-Q Pl - 23 2KC0828 CN-2573-2.1 '
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CN-2573-1.0 K08 3 B ACT Gate MO ST-Q P1 23 t 2KC228B '. CN-2573-1.0 K07 3 B ACT Gate MO ST-Q Pt 23 2KC230A CN-2573-1.3 KOS 2 A/C ACT Check SA FSC-Q U 23. 4 2KC279 2KC280 CN-2573-1.3 E02 2 A/C ACT Check SA FSC-Q - ~U CN-KC-03 23 .] CN-2573-1.3 D13 2 B ACT Gate MO ST-Q PI' 23 2KC305B 2KC315B CN-2573-1.3 L12 2 B ACT Gate MO ST-Q PI 23-
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2KC320A CN-2573-1.3 B10 2 B ACT Gate MO ST-Q Pi CN-KC-01 123
- 2KC332B CN-2573-1.3 E02 2 B ACT Gate MO ST-Q Pl CN-KC-01 23 l 2KC333A CN-2573-1.3 G02 2 B ACT Gate MO ST-Q Pl CN-KC-01 23: !
2KC3388 CN-2573-1.3 D12 2 B ACT Gate MO ST-Q Pi CN-KC-02 23 ~ j 2KC340 CN-2573-1.3 E12 2 A/C ACT Check SA . FSC-Q U CN-KC-03 23-CN-2573-1.3 LOS 2 B ACT Gate MO ST-Q Pt- CN-KC 23 ! l 2KC424B 2KC425A CN-2573-1.3 LO6 2 B ACT Gate MO ST-Q Pi CN-KC-02 23 l Sectum 4.2 KC - 1 of 2 < Rev. 23 06/29/96
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J' l i Unit 2-Catawba Nuclear Station > Insesvice Testing Program TEST TEST i VALVE ACT ACT REOMT REQWT JUSTtF FOR TEST FLOW FLOW AsasE PAS VALVE TYPE TYPE 80 0 .1 80 0 . 2 REUEF REOST DEFEMAL REh8MWLS - ALTEppsATIVES REV VALVE scutsBER DLAGRAAA COOR CLASS CATGRY COMPONENT COOUNG (KC) 2KC4298 - CN-2573-1.5 H03 2 A ACT Globe MO ST-Q l.J/PI 23 2KC430A CN-2573-1.5 J03 2 A ACT Globe MO ST-Q l.J/PI 23 2KCC37A - CN-2573-1.0 C03 3 B ACT Globe MO STO/C-Q Pt 23
.2KCC40B CN-2573-1.0 C10 3 B_ ACT Globe MO STO/C-Q PI 23 i
1 I I l Section 4.2 KC - 2 of 2 Rev.23 06/29/96
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Unit 2- Catawba Nuclear Stahon Inservice Testing Program TEST 7tsT VALVE ACT ACT REQ WT REQ wT JUSTIF FOR TEST PLOW FLOW ASME
**a"*** COOR class CATORY PAS VALVE TYPE TW 98 0 .1 - Iso. 2 REUEFMEQST DEFERML REhuflKS ALTENsATivts REV VALVE teuMBER i
! DIESEL GENERATOR ENGINE COOUNG WATER SYSTEM (KD) 2KD006 CN-2609-1.0 J10 3 C ACT Check SA FSO/C-Q CN-KD-01 23 CN-2609-1.0 - E10 3 C ACT Check SA FSO/C-Q CN-KD.01 23 2KD021 i Section 4.2 KD - 1 of 1 Rev. 23 06/29/96
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Unit 2- Catawba Nuclear Station -{ , insesvece Testing Program . TEST . TEST i PLOW FLOW ASME VALVE ACT. ACT REQ WT REQWT JUSTIF FOR TEST- ' '!
). vmLvt seuMcER DameRAss COOR _ CLASS CATORY PAS
- tLVE TYPE TYPE ' 80 0 .1 80 0 . 2 RELIEF REOST DEPUWWtL REheARKS ' ALTgueATNES - REV a
i ' SPENT FUEL COOUNG (KF) > r
- 2KF1'01B ' - CN-2570-1.0 -H13 2 B ACT Plug MO ST-Q PI ' 23 2KF103A CN-2570-1.0 H12 2- B ACT Plug MO ST-Q Pi .23 6
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1 Unit 2 - Catawba Nuclear Station - Inservice Testing Program TEST TEST FLOW FLOW ASe#E VALVE ACT ACT REQwT MQWT JUST1F FOR TEST
. VALVE peuteSER DRAGRAA4 COOR CLASS CATORY ' PAS VALVE TYPE TYPE N0.1 NO. 2 HELIEF REQST DEFUWW. HEReARKS MTWW6ATIVES REV DIESEL GEN. ENGINE LUBE OIL (LD) aLD002 CN-2609-2.0 F09 3 C ACT Relief SA RV 70 PSIG ~ 23 2LD017 CN-2609-2.0 K09 3 C ACT Check SA FSO/C-Q 23 ?LD018 CN-2609-2.0 J06 3 C ACT Check SA FSO/C-Q - 23 D032 CN-2609-2.2 F09 3 C ACT Relief SA RV 70 PSIG 23 LD047- CN-2609.2.2 KOS 3 C ACT Check SA FSO/C-Q 23
- LD048 CN-2609-2.2 J06 3 C ACT Check SA FSO/C-Q 23 2LD071 CN-2609-2.0 K06 3 C ACT Check SA FSO/C-Q 23 '
_LD072 CN-2609-2.0 J06 3 C ACT Check SA FSO/C-Q 23 iLD078 CN-2609-2.2 K06 3 C ACT Check SA FSO/C-Q 23 2LD079 CN-2609-2.2 . J06 3 C 'ACT Check SA FSO/C-Q 23 l l l Section 4.2 LD - 1 of 1 Rev. 23 06/29/96
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f k Unit 2- Catawba Nuclear Station Inservice Testing Program TEST TEST' FLOW FLOW A5hAE VALVE ACT .ACT REQ MT REQMT JUST17 FOR TEST' VALVE ttuaABER DIAGRAho COOR class CATORY PAS VALVE TYPE TYPE 98 0 . 1 peo. 2 ' REUEPREQST DEFEfWWL ftEMAfKS ' ALTEppsATWES REV RADIATION MONITORS (MI) 2MIMV6470 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23 2MIMV6471 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23 2MIMV6480 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23 2MIMV6481 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23 2MIMV6490 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23 2MIMV6491 CN-1499.03-09.02 K10 2 A ACT Needle MA U 23 2MISV5230 CN-2499-M119 2 A ACT Globe SO ST/FT-Q U/PI 23 2MISV5231 CN-2499-M119 2 A ACT Globe SO ST/FT-Q U/PI 23 2MISV5232 CN-2499-M119 2 A ACT Globe SO ST/FT-Q - U/PI 23 2MISV5233 CN-2499-M119 2 A ACT Globe SO ST/FT-Q U/PI 23 Section 4.2 . MI- 1 of 1 Rev. 23 06/29/96 _ _ - _ - _ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - - _ _ _ _ _ - - _ - - _ _ _ _ - _ - _ - - - - _ _ - _ _ _ _ _ _ _ - _ _ - - _ _ .. . . . - . - . _~ -
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Unit 2- Catawba Nuclear Station inservica Testing Program TEST TEST . ACT MQwT MQwT JusTIF FOR TEST R.OW FLOW ASME VALVE ACT CLASS CATORY PAS VALVE TYPE TYPE 90 0 .1 No. 2 REUEF MOST DEF94WL REMAfWLS ALT 950ATIVES MV. VMVE NUMSER OtAGRAM COOR BORON RECYCLE (NB) GO4 2 A ACT Globe MO ST-Q U/PI 23 2NB2600 CN-2556-2.0 C@ 2 AIC ACT Check SA FSO/C-Q U CN-NB411 23 2NB262 CN-2556-2.0 5 l i t i MB - 1 of 1 Section 4.2 , Rev. 23 06/29/96
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(s Unit 2 - Catawba Nuclear Station Inservice Testing Program VALVE ACT ACT 1d7 REQ T JUSTtF FOR TEST , FLOW FLOW ASME COOR CLASS CATORY PAS VALVE TYPE TYPE NO.1 80 0 . 2 RELIEF REQsf DEFB4RAL RDdMULS ALTERNATIVES REV. i VALVE NtJMSEA OLAORAM NUCLEAR SAMPUNG SYSTEM (NM) K03 2 A ACT Globe MO ST-Q U/PI 23 2NM003A CN-2572-1.0 J03 2 A ACT Globe MO ST-Q U/PI 23 2NM006A CN-2572-1.0 CN-2572-1.0 K06 2 A ACT Globe MO ST-Q U/PI 23 2NM007B CN-2572-1.0 K11 2 A ACT Gobe MO ST-Q U/PI 23 2NM022A CN-2572-1.0 K12 2 A ACT Globe MO ST-Q U/PI 23 2NM025A ' 2NM0268 CN-2572-1.0 K08 2 A ACT Globe MO ST-Q U/PI 23 2NM069 Crd-2572-1.1 G10 2 A ACT Relief SA U RV 700 PSIG 23 2NM072B CN-2572-1.1 106 2 A ACT Gobe MO ST-0. U/PI 23 2NM0758 CN-2572-1.1 10 8 2 A ACT Gobe MO ST-Q U/PI 23 2NM078B CN-2572-1.1 109 2 A ACT Globe MO ST-Q U/PI 23 - 2NM081B CN-2572-1.1 11 1 2 A ACT Globe MO ST-Q U/PI 23 2NM082A CN-2572-1.1 E09 2 A ACT Gobe MO ST-Q U/Pl 23 2NM187A CN-2572-1.4 K02 2 B ACT Globe MO ST-Q Pl 23 , 2NM190A CN-2572-1.4 K02 2 B ACT Gobe MO ST-Q Pt 23 2NM191B CN-2572-1.4 102 2 B ACT Globe MO ST-Q Pt 23. 2NM197B CN-2572-1.4 K05 2 B ACT Gobe MO ST-Q PI 23 2NM2008 CN-2572-1.4 K06 2 B ACT Globe MO ST-Q Pi 23 2NM201A CN-2572-1.4 10 6 2 B ACT Globe MO ST-Q PI 23 2NM207A CN-2572-1.4 K08 2 B ACT Globe MO ST-Q Pl 23 2NM210A CN-2572-1.4 K09 2 B ACT Gobe MO ST-Q Pt 23 2NM211B CN-2572-1.4 109 2 B ACT MO ST-Q PI 23 2NM217B CN-2572-1.4 K11 2 B ACT Gobe MO ST-Q. Pt 23 2NM220B CN-2572-1.4 K13 2 B ACT Gobe MO ST-Q PI 23 2NM221A CN-2572-1.4 11 2 2 B ACT Globe MO ST-Q Pl 23 2NM424 CN-2572-1.0 J03 2 A/C ACT Check SA FSC-Q U 23 2NM425 CN-2572-1.0 K12 2 A/C ACT Check SA FSC-Q U 23 Section 4.2 NM - 1 of 1 Rev.23 06/29/96
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O o ~ Unit 2 - Catawba Nuclear Station Inservice Testing Program TEST TEST PLOW FLOW AsaAE VALVE ACT ACT REQ WT REQ WT .%TIF FOR TEST COOR CLASS CATORY PAS VALVE TYPE TYPE 80 0 .1 too.2 REUEF REQST DEFEEWLAL REheARKS ALTEpueATIVES ' REV VALVE 9euemSER DeAGRAM REACTOR COOLANT SYSTEM (NC) 2NC001 CN-2553-1.1 K03 1 C ACT Relief SA RV 2485 PSIG 23 2NC002 CN-2553-1.1 K04 1 C ACT Relief SA RV 2485 PSIG 23 2NC003 CN-2553-1.1 K06 1 C ACT Relief SA RV . 2485 PSIG 23 2NC0318 CN-2533.1.1 F04 1 B ACT Gate MO ST-Q PI 23 2NCO320 CN-2553-1.1 G04 1 B ACT Globe AO STFT-Q Pl CN-NC-02 23 2NC033A CN-2553-1.1 F03 1 B ACT Gate MO ST-Q PI 23 2NC034A CN-2553-1.1 G03 1 B ACT Globe AO ST/FT-Q PI CN-NC-02 23 .- 2NC0358 CN-2553-1.1 F02 1 B ACT Gate MO ST-Q Pt 23 - 2NC0368 CN-2553-1.1 G02 1 B ACT Globe AO ST/FT-Q Pi CN-NC-02 23-2NC053B CN-2553-1.1 K11 2 A ACT Globe MO ST-Q U/Pt 23 2NC054A CN-2553-1.1 - K09 2 A ACT Globe MO - ST-Q U/PI 2NC0568 CN-2553-1.1 11 3 2 A ACT Gate MO ST-Q U/Pl 23 2NC057 CN-2553-1.1 11 2 2 A/C PAS Check SA FSO/C-Q U CN-NC-01 23-
. 2NC141 CN-2553-1.3 J08 2 A PAS Gate MA U 23 2NC142- CN-2553-1.3 K08 2 A PAS Gate MA U 23 2NC1958 CN-2553-1.3 E07 2 A ACT Gate MO ST-Q U/PI 23 2NC196A CN-2553-1.3 D07 2 A ACT Gate MO ST-Q U/PI 23 2NC250A CN-2553-1.1 LO7 1 B ACT Globe MO ST-Q Pi CN-NC-03 23 2NC251B CN-2553-1.1 LO7 1 B ACT Globe MO ST-Q Pl CN-NC-03 23 2NC252B CN-2553-1.1 K07 1 B ACT Globe MO ST-Q Pl CN-NC-03 23 2NC253A CN-2553-1.1 K07 1 B ACT Globe MO ST-Q Pl CN-NC-03 23 -
Section 4.2 NC - 1 of 1 : Rev. 23 06/29/96
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Unit 2 - Catawba Nuclear Station . Inservice Testing Program TEST TEST VALVE ACT ACT REQwT -' REGMT JUK'tF FOR ' TEST FLOW FLOW ASME
.COOR CLASS CATORY PAS VALVE TYPE - TYPE 10 0 .1 sec. 2 REUEF IEOST DEFWunAL REntAfuls . ' ALTsueAftWES REV?
- VALVEfeUMBER DIAGRAM RESIDUAL HEAT REMOVAL (ND) 2ND001B . CN-2561-1.0 L13 1 A ACT Gate MO ST-Q -LT/P1 CN-ND-01 l23 CN-2561-1.0 J13 1' A ACT ' Gate MO ST-Q LT/PI CN-ND-01 -' 23 2ND002A CN-2561-1.0 2 C PAS Relief SA RV 450 PSIG .23 2ND003 11 3 CN-2561-1.0 G10 2 C ACT Check SA FSO/C-Q CN-ND-03 23 "
2ND010 2ND025A CN-2561-1.0 E13 2 B ACT Globe MO ST-Q Pi 23 2ND026 CN-2561-1.0 G04 2 B ACT Butterity 'AO ST/FT-Q PI 23 2ND027 CN-2561-1.0 J06 2 B ACT Butter 9y AO. ST/FT-Q Pl .23-2ND028A CN-2561-1.0 10 4 2 B ACT Gate MO ST-Q Pi CN-ND-05 .23 2ND031 CN-2561-1.0 G02 2 C PAS Relief SA RV 600 PSIG 23
- 2ND032A CN-2561-1.0 E03 2 B ACT Gate MO ST-Q Pi CN-ND-04 ~ 23 2ND035 CN-2561-1.0 D02 2 C PAS Relief SA RV 600 PSIG 23 I 2ND0368 CN-2561-1.1 L13 1 A ACT Gate MO ST-Q LT/PI CN-ND-02 23 2ND037A CN-2561-1.1 J13 1 A ACT Gate MO ST-Q LT/PI CN-ND-02 23 2ND038 CN-2561-1.1 11 3 2 C PAS Relief SA RV 450 PSIG : 23 2ND044 CN-2561-1.1 G10 2 C ACT Check SA FSOK:-Q CN-ND 03 23-2ND0598 CN-2561-1.1 E13 2 B ACT Globe MO' ST-Q PI 23
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2ND060 CN-2561-1.1 G04 2 B ACT Butterfly AO ST/FT-Q Pl '23 2ND061 CN-2561-1.1 J06 2 B ACT Butterfly AO ST/FT-Q Pi 23 2ND064 CN-2561-1.1 H02 2 C PAS Relief SA RV . 600 PSIG 23: 2ND0658 CN-2561-1.1 E03 2 B ACT Gate MO ST-Q Pl CN-ND-04 23 ' 4 Section 4.2 ND'- 1 OI1 Rev.23 06/29/96 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ _ _ ___ _. - . . - . . . _ , _ . _ . _ _ = _ _ _ _ . _ . - .._ -
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Unit 2- Catawba Nuclear Station
' Inservice Testing Program .
TEST TEST FLOW ASME VALVE ACT ACT ' REOWT . REQ wT .: JUSTIF FOR - TEST FLOW VALVE feutASER DeAGRMA COOR CLASS CATORY PAS VALVE TYPE TYPE 50 0 .1 Iso. 2 REUEF REOST DEFWWWL I4hMfSLS ALTEfmATIVES REV ICE CONDENSER REFRIGERATION (NF) -- 2NF228A'- . CN-2558-2.0 H14 .2 A ACT Gate AO ST/FT-Q L#Pi '23 2NF229 CN-2558-2.0 F14 2 NC ACT Check SA ' FSC-Q U CN-NF-01 23 2NF2338 CN-2558-2.0 L10 2 A ACT Gate MO ST-Q . LNPt 23 2NF234A CN-2558-2.0 L12 2 A ACT Gate AO ST/FT-Q UtPi '23 2NF235 CN-2558-2.0 K10 2 NC ACT Check SA FSO/C-Q U 23
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Section 4.2 NF- 1 of 1 Rev. 23 06/29/96 . . ~ . _ _ .-.
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V Unit 2-Catawba Nuclear Station Inservice Testing Program TEST ' TEST
' FLOW ROW ASME VALVE ACT ACT MOWT REQ WT JUST1F FOR ' TEST DLAGRAM COOR CLASS CATGRY PAS VALVE TYPE TYPE NO.1 NO. 2 RELIEF REQST DEFSUML REMARKS ' ALTERNATIVES REV VALVE NUMGER SAFETY INJECTION SYSTEM (NI) 2NICO9A CN-2562-1.0 C09 2 B ACT Gate MO ST-Q Pl CN-NI-01 23 2N10100 CN-2562-1.0 C06 2 B ACT Gate MO ST-Q Pl CN-NI-01 23-
' 2N1012 CN-2562-1.0 F08 2 C ACT Check SA FSO/C-Q CN-NI 23-2N1015 CN-2562-1.0 11 1 1 -C ACT Check SA FSO/C-Q CN-NI-03 23 2N1017 CN-2562-1.0 10 9 1 C ACT Check SA FSO/C-Q CN-NI-03 23 2N1019 CN-2562-1.0 10 7 1 C ACT Check SA FSO/C-Q CN-NI-03 . 23 2N1021 CN-2562-1.0 10 5 1 C ACT Check SA FSO/C-Q CN-NI-03 23 2N1047A CN-2562-1.1 ' K09 2 A ACT Globe MO ' ST-Q LJ/Pi 23 2NIO48 CN-2562-1.1 K08 2 NC ACT Check SA FSO/C-Q LJ CN-NI-05 23 '
2N1054A CN-2562-1.1 G02 1 B 'ACT Gate MO Pt 23 2N1059 CN-2562-1.1 D02 1 NC ACT Check SA FSO/C-Q LT CN-NI-06 23 2N1060 CN-2562-1.1 CO2 1 NC ACT Check SA FSO/C-Q LT CN-NI-04 23 2N10658 CN-2562-1.1 F05 1 B ACT Gate MO PI 23 2N1070 CN-2562-1.1 DOS 1 NC ACT Check SA FSO/C-Q LT CN-NI-06 23' 2N1071 CN-2562-1.1 C05 1 NC ACT Check SA FSO/C-Q LT CN-NI-04 23' 2NIO76A CN-2562-1.1 G07 1 B ACT Gate MO PI 23 2N1081 CN-2562-1.1 D07 1 NC ACT Check SA FSO/C-Q LT CN-NI-06 23 2N1082 CN-2562-1.1 C07 1 NC ACT Check SA FSO/C-Q LT CN-NI-04 23 i 2NIO888 CN-2562-1.1 G10 1 B ACT Gate MO Pl 23 2NIO93 CN-2562-1.1 D10 1 NC ACT Check SA FSO.0-Q LT CN-NI-06 23 2N1094 CN-2562-1.1 C10 1 NC ACT Check SA FSO/C-Q LT CN-NI-04 23
' 2N1095A CN-2562-1.1 F13 2 A ACT Gate MO ST-Q LJ/PI 23 2N10968 CN-2562-1.1 H13 2 A ACT Globe MO ST-Q LJiPI '23 2N11000 CN-2562-1.2 G13 2 B ACT Gate MO ST-Q Pl CN-NI-08 23 ,
2N1101 CN-2562-1.2 G13 2 C ACT Check SA FSO/C-Q LT CN-N1-07 23-2N1102 CN-2562-1.2 F13 2 C PAS Relief SA RV ' 220 PSIG 23 2N1103A CN-2562-1.2 11 3 2 B ACT Gate MO ST-Q Pt 23 2N1114 CN-2562-1.2 10 8 2 C ACT Check SA FSO/C-Q 23 , l Section 4.2 ~ NI - 1 of 4 Rev.23 06/29/96
. _ __. _ _ _ _ . . _ _ . ,y Unit 2 - Catawba Nuclear Station Inservice Testing Program i TEST TEST .
FLOW ASME VALVE ACT ACT REQMT REQW T JUST1F FOR TEST FLOW
'COOR CLASS CATGRY PAS VALVE TYPE TYPE 90 0 .1 . NO. 2 REUEF REQST ' DEFERRAL REMARKS ALT 9ueATTVES " REW l : VALVE ssVMSER DIAGRAM SAFETY INJECTION SYSTEM (NI) 2N1115A CN-2562-1.2 H08 2 B ACT Globe MO ST-Q Pl -23 2N1116 CN-2562-1.2 J08 2 C ACT Check SA FSO/C-Q CN-NI-10 23 2N!118A CN-2562-1.2 H06 2 B ACT Gate MO ST-Q PI 23 2NI119 CN-2562-1.2 K06 2 C PAS Relief SA RV 1900 PSIG 23 2N11200 CN-2562-1.2 10 5 2 A ACT Globe MO ST-Q LJ/Pl 23 2N1121A CN-2562-1.2 JOS 2 B ACT Gate MO ST-Q Pl CN-NI-21 23 '
- 2N11228 CN-2562-1.2 K04 2 B ACT Globe MO ST-Q Pt 23 2N1124 . CN-2562-1.2 104 1 NC ACT Check SA FSO/C-Q LT CN-NI-11 23 2N1125 CN-2562-1.2 H04 1 A/C PAS Check SA FSO/C-Q LT 23 2NB126 CN-2562-1.2 101 1 NC ACT Check SA FSO/C-Q LT CN-Ni-11 23 2N1128 CN-2562-1.2 K04 1 A/C ACT Check SA FSO/C-Q LT CN-NI-11 23 2N1129 CN-2562-1.2 J03 1 NC PAS Check SA FSO/C-Q LT 23 2N1134 CN-2562-1.2 K01 1 NC ACT Check SA FSO/C-Q LT CN-NI-11 -23 2N1135B CN-2562-1.2 E13 2 B ACT Gate MO ST-Q Pt 23 2N11368 CN-2562-1.2 D13 2 B ACT Gate MO ST-Q Pi CN-NI-19 23 2N1143 CN-2562-1.2 E08 2 C ACT Check SA FSO/C-Q 23 2N1144A CN-2562-1.2 F08 2 B ACT Globe MO ST-Q Pl CN-NI-22 23 2N11478 CN-2562-1.2 G10 2 B ACT Globe MO ST-Q Pi CN-NI-09 23 2N1148 CN-2562-1.2 D08 2 C ACT Check SA FSO/C-Q CN-NI-10 23 2N11508 CN-2562-1.2 F06 2 B ACT Gate MO ST-Q PI 23 2N1151 CN-2562-1.2 E06 2 C PAS Relief SA RV 1900 PSIG 23 2NB152B CN-2562-1.2 DOS 2 B ACT Gate MO ST-Q Pl CN-Ni-21. 23 2N1153A CN-2562-1.2 D04 2 B ACT Globe MO ST-Q PI 23 2N1154B CN-2562-1.2 H03 2 B ACT Globe MO ST-Q Pi 23 2N1156 CN-2562-1.2 E03 1 NC ACT Check SA FSO!C-Q LT CN-NI-11 23 2N1157 CN-2562-1.2 E01 1 A/C ACT Check SA FSO/C-Q LT CN-NI-11 23 2N1159 CN-2562-1.2 CO3 1 NC ACT Check SA FSO/C-Q LT CN-NI-11 23 2N1160 CN-2562-1.2 C01 1 NC ACT Check SA FSO/C-Q LT CN-NI-11 23 Section 4.2 NI-2 of 4 Rev. 23 06/29/96
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.1 Unit 2- Catawba Nuclear Stahon
. Inservice Testing Program TEST TEST FLOW VALVE ACT ACT REQ wT REOMT . JUSTIF FOR . ' TEST-M.0W ASRAE DeAGRAfd COOR CLASS CAteRY PAS VALVE TYPE TYPE 38 0 .1 000.2 fEEF REOST - DEPWutAL IIsteApSLs ALTESeATWSS ,SEV-
- VALVE IsuneSER SAFETY INJECTION SYSTEM (NI) 2Nt161 - CN-2562-1.3 2 C PAS Relief SA RV 1900 PSIG 23 .
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SA FSO/C-Q CN-NI-13 . ; 23 2NI167 CN-2562-1.3 GOS 1 A/C ACT Check . LT -
' 2N1169 CN-2562-1.3 G09 1 A/C ACT . Check SA FSO/C-Q LT CN-NI-13 - 23 :'
2N1171 CN-2562-1.3 G12 1 A/C ACT Check SA- FSO/C-Q LT CN-Ni -
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2N1173A ' CN-2562-1.3 E10 2 B ACT Gate MO- ST-Q Pi CN-Ni-15 23 ; , 2N1175 - CN-2562-1.3 F11 1 A/C ACT Check SA FSO/C-Q LT CN-Ni-14 23 2N1176 CN-2562-1.3 F09 1 A/C ACT Check SA FSO/C-Q LT . CN-NI-14 23 - .
- 2N11788 CN-2562-1.3 E04 2 B ACT Gate MO ' ST-Q Pi CN-NI-15 = 23' ' 2N1180 CN-2562-1.3 F05 1 A/C ACT Check SA FSOtC-Q LT . CN-NI 23 .
2NI181 CN-2562-1.3 F04 1 A/C ACT Check SA FSO/C-Q LT CN-NI-14 ' 23
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2Nt185A CN-2562-1.3 C05 2 B ACT Gate MO ST-Q Pl. . CN-NI-17 . 23
' 2N1332A CN-2562-1.2 L12 2 B ACT Gate MO ' ST-Q Pl CN-NI-18 - 23 2NI3338 CN-2562-1.2 K12 2 B ACT Gate MO ST-Q Pl CN-N1-18 23 ;
2N13348 CN-2562-1.2 K11 -2 B ACT Gate MO ST-Q PI- CN-NI-23 23 2Nt342 CN-2562-1.2 D13 2 C ACT Check SA FSO/C-Q CN-NI-20 23" 2N1351 CN-2562-1.0 11 1 1 C ACT Check SA FSO/C-Q CN-NI .23 ' 2N1352 CN-2532-1.0 10 9 1 C ACT Check SA FSO/C-Q CN N143 - 23 . 2N1353 CN-2562-1.0 10 7 1 C ACT Check SA FSO/C-Q . CN-NI-03 23 , 2N1354 CN-2562-1.0 10 5 1 C ACT Check SA FSO/C-Q ~ CN-NI-03 23L 2N1391 CN-2562-1.1 C03 2 A ACT Globe AO LT L 2N1392 CN-2562-1.1 C04 2 A ACT Globe AO LT 23 i
. 2N1393 CN-2562-1.1 ~ CD8 2 A ACT Globe AO LT 23 2N1394 CN-2562-1.1 C11 2 A ACT Globe AO LT 23 23
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2N1395 CN-2562-1.2 E01 2 A ACT Globe AO LT Section 4.2 i NE - 3 of 4 [ Rev.23 06/29/96 [
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'x a Unit 2 - Catawba Nuclear Station -
Inservice Testing Program TEST TEST FLOW FLOW ASME VALVE ACT ACT MOWT REQ WT JUSTIF FOR TEST VALVE NUMSER D6AGRAM . COOR CLASS CATORY PAS VALVE TYPE TYPE NO.1 NO. 2 REufF MOST DEF9WuL RERSMBLS MTUusATIVES MV SAFETY INJECTION SYSTEM (NI) 2N1396 CN-2562-1.2 K01 2 A ACT Globe AO- LT 23 2N1397 CN-2562-1.2 101 2 A ACT Globe AO LT 23 2Nt398 CN-2562-1.2 C01 2 A ACT Globe AO LT ..23. 2N1438A . CN-2562-1.1 K01 2 B ACT Globa MO ST-Q Pi - 23 2N1439B CN-2562-1.1 K05 2 B ACT Globe MO ST-Q Pi - 23' 2N1471 CN-2562-1.1 F13 2 A ACT Check SA LJ 23 i i i E i Section 4.2 NI- 4 of 4 Rev.23 06/29/96 . 4 4 . . . . ._ ._ __ __ ___________m
L) V U Unit 2- Catawba Nuclear Station Inservice Testing Program TEST TEST FLOW FLOW ASME VALVE ACT ACT REQ 1dT REQ'MT JUSTtF FOR TEST' VALVE NUMSER ORAGRAM COOR CLASS CATGRY PAS VALVE TYPE TYPE NO.1 NO. 2 RELEF REQST - DEFEWIAL REMARKS ALTHWeATWES - REV CONTAINMENT SPRAY (NS) 2NS001B CN-2563-1.0 C13 2 B ACT Gate MO ' ST-Q Pi 23 2NS0038 CN-2563-1.0 E13 2 B ACT Gate MO ST-Q Pt 23 2NS004 CN-2563-1.0 D13 2 C ACT Check SA FSO M CN-NS-01 ' 23' 2NS012B CN-2563-1.0 COS 2 B ACT Gate MO ST-Q Pi 23
. 2NS013 CN-2563-1.0 C03 2 C ACT Check SA FSO/C-Q CN-NS-02 23 -
2NS015B CN-2563-1.0 EOS 2 B ACT Gate MO ST-Q PI 23 2NS016 CN-2563-1.0 E03 2 C ACT Check SA FSO/C-Q CN-NS-02 ~23-2NS018A CN-2563-1.0 J13 2 B ACT Gate MO ST-Q PI 23-2NS020A CN-2563-1.0 11 3 2 B ACT Gate MO ST-Q Pt 23 2NS021 CN-2563-1.0 11 3 2 C ACT Check SA FSO/C-Q CN-NS-01 23 2NS029A CN-2563-1.0 10 5 2 B ACT Gate MO ST-Q PI 23 2NS030 CN-2563-1.0 10 2 2 C ACT Check SA FSO/C-Q - CN-NS-02 23L 2NS032A CN-2563-1.0 K05 2 B ACT Gate MO ST-Q Pl 23 2NS033 CN-2563-1.0 K03 2 C ACT Check SA FSO/C43 CN-NS-02 23 2NS0388 CN-2563-1.0 F05 2 B ACT Gate MO ST-Q Pl CN-NS-03 23 2NSO41 CN-2563-1.0 F03 2 C ACT Check SA FSO/C-Q CN-NS-02 ' 23 2NSO43A CN-2563-1.0 H05 2 B ACT Gate MO ST-Q PI CN-NS-03 23 - 2NSO46 CN-2563-1.0 H03 2 C ACT Check SA FSO/C-Q CN-NS-02 23 2NSO98 CN-2563-1.0 JO9 2 C ACT Check SA FSO/C-Q CN-NS-01 23 2NSO99 CN-2563-1.0 D09 2 C ACT Check SA FSO/C-Q CN-NS-01 23 Section 4.2 NS - 1 of 1 Rev. 23 06/29/96
m ~. ,m Unit 2 - Catawba Nuclear Station Inservice Testing Program TEST TEST - FLOW FLOW ASME VALVE ACT ACT REQ'MT REQ wT JUSTIF FOR TEST VALVE asVMSER DIAGRAM COOR CLASS CATGhY PAS VALvt TYPE TYPE tsO.1 eso. 2 REUEF REQST DEFERRAL REMARKS ALTERNATlWES REV CHEMICAL & VOLUkE CONTROL (NV) 2NV001A CN-2554-1.0 H02 1 B ACT Gate AO ST/FT-Q Pi CN-NV-12 -23 2NV002A CN-354-1.0 H02 1 B ACT Gate AO ST/FT-Q Pl CN-NV-12 23 2NV010A CN-2554-1.0 H08 2 B ACT Gate AO ST/FT-Q Pl CN-NV . 23 2NV011A CN-2554-1.0 10 9 2 B ACT Gate - AO ST/FT-Q Pi CN-NV-11 23 2NV013A CN-2554-1.0 G08 2 B ACT Gate AO ST/FT-Q Pi CN-NV-11 23 2NV014 CN-2554-1.0 G10 2 A ACT Relief SA U RV 600 PSIG 23 2NV0158 CN-2554-1.0 H12 2 A ACT Globe MO ST-Q LJ/PI CN-NV-01 23 2NV087 CN-2554-1.0 CD8 2 C ACT Relief SA RV 150 PSIG '23 2NV089A CN-2554-1.0 B09 2 B ACT Gate MO ST-Q CN-NV-02 23 2NV090 CN-2554-1.0 D09 2 A/C ACT Check SA FSC-Q U 23 2NV0918 CN-2554-1.0 B11 2 B ACT Gate MO ST-Q Pi CN-NV-02 23 2NV188A CN-2554-1.1 C05 2 B ACT Gate MO ST-Q PI CN-NV-03 23 2NV189B CN-2554-1.1 C04 2 B ACT Gate MO ST-Q Pl CN-NV-03 23 2NV202B CN-2554-1.6 D01 2 B ACT Globe MO ST-Q Pi CN-NV-07 23 2NV203A CN-2554-1.6 D01 2 B ACT Globe MO ST-Q Pl CN-NV-07 23 2NV205 CN-2554-1.1 G04 2 C ACT Relief SA RV 150 PSIG 23 2NV206 CN-2554-1.6 C03 2 B ACT Plug AO PI 23 2NV218 CN-2554-1.6 C06 2 B ACT Plug AO PI 23 , 2NV220 CN-2554-1.1 G04 2 C ACT Check SA FSO-O 23 2NV222 CN-2554-1.1 E06 2 C ACT Relief SA RV 220 PSIG 23 2NV223 CN-2554-1.1 H07 2 C ACT Relief SA RV 75 PSIG 23 2NV252A CN-2554-1.7 K11 2 B ACT Gate MO ST-Q Pi CN-NV-10 23 2NV253B CN-2554-1.7 K12 2 B ACT Gate MO ST-Q Pl CN-NV-10 23 2NV254 CN-2554-1.7 K12 2 C ACT Check SA FSO/C-Q CN-NV-05 23 2NV268 CN-2554-1.7 10 5 2 C ACT ' heck C SA FSO/C-Q '23 2NV270 CN-2554-1.7 10 5 2 C ACT Check SA FSO/C-Q CN-NV-06 23 2NV273 CN-2554-1.7 E14 2 C ACT Relief SA RV 220 PSIG 23 2NV288 CN-2554-1.7 E05 2 C ACT Check SA FSO/C-Q 23 Section 4.2 NV - 1 of 2 Rev. 23 06/29/96
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4 v g Unit 2- Catawba Nuclear Station Insesvice Testing Program TEST TEST ! FLOW ROW ASRAE VnVE Ac7 ACT nEOWT nEQwT . JUSTW Fon TEST 1! v=ve nuassen Oimenm coon- ctass cAfony eas v=ve Tves Tyn no.s no. 2 neuer naosi ceFenna nennasms mTameATwas -- nev i CHEMICAL & VOLUME CONTROL (NV) .l 2NV290 CN-2554-1.7 DOS 2 C ACT Check SA FSO/C-Q CN-NV-C0 23 t
. i 2NV312A CN-2554-1.2 KOS 2 B ACT. Gate MO ST-Q Pl CN-NV-04 23-2NV3148 ' CN-2554-1.2 K06 2 B ACT Gate MO ST-Q Pi CN-NV.04 23 i 2NV813 CN-2554-1.7 C12 2 C ACT; Check SA FSCWC-Q CN-NV-08 23 .
2NV865A CN-2554-1.8 H01 2 B ACT Globe MO ST-Q PI 23 - j 2NV872A CN-2554-1.8 F08 2 A ACT Globe MO ST-Q U/Pi 23" ] I , ' 2NV874 CN-2554-1.8 F10 2 AIC ACT Check SA FSC-Q U CN-NV-09 23 . t r A v r
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a Q Unit 2- Catawba Nuclear Station Insennce Testing Program
. TEST TEST l FLOW ' flow I Asant VALVE ACT : ACT REOMT REQwT JusTIF FOR TEST
-- watvE -m osaoRams coOR class cAToRv pas vatvE TYPE TYPE - 80 0.1 80 0 . 2 REUEF REOST ' DEFERRAL RERAARKS - ALTsusAftvtB REW .
CONTAINMENT PENETRATION VALVE WJECTION WATER SYSTEM (NW) . l- -' l' 2NWOO6 CN-2569-1.0 G12 2 C ACT Check SA FSO-Q CN-NW-01 2NWOO8A . CN-2569-1.0 G13 2 B ACT - Gate SO ST/FT-Q ' Pt 23: 1 2NWO13A CN-2569-1.0 E09 2 'B ACT Gate SO ST/FT-Q Pt 23' 2NWO17 CN-2569-1.0 E11 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NWO20A CN-2569-1.0 F00 2 B ACT Gate SO ST/FT-Q ' Pt 23.
- 2NWO21 CN-2569-1.0 E12 2 C ACT Check SA FSOKXI CN-NW-02 2NWO24 CN-2569-1.0 E13' 2 C ACT Check SA FSOdC-Q CN-NW-02
- 23.
2NWO27 CN-2569-1.0 E14 2 C ACT Check SA FSOdC-Q CN-NW-02 23-
- 2NWO35A- CN-2569-1.0 H09 2 B ACT Globe MO ST-Q Pt 23 4 2NWO37 CN-2569-1.0 10 9 2 C ACT Check SA FSOdC-Q CN-NW-02 - 23 .l t
2 C ACT Check SA FSOdC-Q CN-NW-02 23
. 2NWO40 CN-2569-1.0 J11 }
2NWO43 CN-2569-1.0 J10 2 C ACT Check SA FSO/C-Q CN-NW 23 2NWO46A CN-2569-1.0 K09 2 B ACT Gate SO . ST/FT-Q Pt ' 23- $ 2NWO47 CN-2569-1.0 L10 2 C ACT Check SA FSOJC-Q CN-NW-02 '. 23: ;
~ 2NWO50 CN-2569-1.0 L11 2 C ACT Check SA FSOdC-Q CN-NW-02 23~
2NWO61B CN-2569-1.0 G02 2 B ACT Gate SO ST/FT-Q Pl 23 c . 2NWO63 ' CN-2569-1.0 G04 2 C ACT Check SA FSO-Q CN-NW-01 23 ] 2NWO688 CN-2569-1.0 EOS 2 B ACT Gate SO ST/FT-Q Pi ..23- , 2NWO698 CN-2569-1.0 F06 2 B ACT Gate SO ST/FT-Q Pt 23 .[ 2NWO70 CN-2569-1.0 E05 2 C ACT Gate SA FSO/C-Q CN-NW-02 23 2NWO74 CN-2569-1.0 EOS 2 C ACT Check SA FSOdC-Q CN-NW ' 23 i , 2NWO77 CN-2569-1.0 E04 2 C ACT Check SA FSO/C-Q CN-NW-02 23I , 2NWO80 CN-2569-1.0 'E03 2 C ACT Check SA FSO/C-Q CN-NW-02 ' 23 2NWO86 CN-2569-1.0 E01 2 C ACT Check SA FSOtC-Q CN-NW-02 23 - 2NWO89 CN-2569-1.0 C05 2 C ACT Check SA FSO/C-Q CN-NW-02 23 .! 2NWO92 : CN-2569-1.0 COS 2 C ACT Check SA FSOdC-Q CN-NW-02 ' : 23 2NWO95 CN-2569-1.0 C04 2 C ACT Check SA FSO/C-Q CN-NW-02 . 23 2NWO90 CN-2569-1.0 CO2 2 C ACT- Check SA FSO/C-Q CN-NW-02 23 4 Section 4.2 NW- 1 of 4 i Rev. 23 06/29/96
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- . t Unit 2 - Catawba Nuclear Station Inservice Testing Program .
TEST TEST . PLOW FLOW ASBAE VRVE 'ACT ACT- REO MT- REQ'esT JUSTIF POR . _ - TEST CLASS CATSRY PAS VALVE TYPE TYPE seo.s sec. 2 ReJEF REOST - DErguta menAfus ALTWunATWES sev , VALVE leWhSER DIAGRAh4 COOR CONTAINMENT PENETRATION VALVE INJECTION WATER SYSTEM (NW)
' 2NW101 CN-2569-1.0 C01 2 C ACT Check SA ' FSO M CN-NW-02 ~ 23~
2NW105B ' CN-2569-1.0 H06 2 B ACT Globe MO ST-Q Pt 23 ~ 2NW107 CN-2569-1.0 10 6 2 C ACT Check SA FSO/C-Q CN-NW-02 23
- - 2NW109 CN-2569-1.0 K05 2 C ACT Check SA FSOtC-Q CN-NW-02 23
- 2NW1108 , CN-2569-1.0 K06 2 B ACT Gate SO. ST/FT-Q Pt 23 2NW111 CN-2569-1.0 JOS 2 C ACT Check SA FSO/C-Q ' CN-NW-02 23 '-
2NW114 CN-2569-1.0 LOS 2 C ACT Ctw* SA FSOC-Q CN-NW-02 23 2NW120 CN-2569-1.0 JOS 2 C ACT Cneck SA FSOC-Q CN-NW-02 23' 2NW121 ' CN-2569-1.0 E01 2 C ACT Check SA FSOtC-Q ' CN-NW-02 23 2NW123 CN-2569-1.0 E03 2 C ACT Check SA FSOC-Q CN-NW-02 ~23 2NW124 CN-2569-1.0 E04 2 C ACT Check SA FSOC-Q CN-NW-02 - 23 2NW125 CN-2569-1.0 E05 2 C ACT Check SA FSOC-Q CN-NW-02 23
- 2NW126 CN-2569-1.0 EOS 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW127 CN-2569-1.0 C01 2 C ACT Check SA FSO/C-Q CN-NW-02 23' 2NW128 CN-2569-1.0 CO2 2 C ACT Check SA FSOC-Q CN-NW-02 23'
- 2NW129 CN-2569-1.0 C04 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW130 CN-2569-1.0 C05 2 C ACT Check SA FSOC-Q CN-NW-02 23 2NW131 CN-2569-1.0 C05 2 C ACT Check SA FSOC-Q CN-NW-02 23 2NW132 CN-2569-1.0 K10 2 C ACT Check SA FSOC-Q - CN-NW-02 _ :23 2NW133 CN-2569-1.0 K10 2 C ACT Check SA. FSOC-Q CN-NW-02 23 2NW135 CN-2569-1.0 J10 2 C ACT Check' SA FSOC-Q CN-NW-02 ' '23 -
2NW136 CN-2569-1.0 J11 2 C ACT Check SA FSOC-Q CN-NW-02 ' ~23 2NW138 CN-2569-1.0 E11 2 C ACT Check SA FSOC-Q . CN-NW-02 23 2NW139 CN-2569-1.0 E12 2 C ACT Check SA FSOdC-Q - CN-NW 23 2NW140 - CN-2569-1.0 E13 2 C ACT Check SA FSOtC-Q CN-NW-02 ' 23 2NW141 CN-2569-1.0 E14 2 C ACT Check SA FSO/C-Q CN-NW-02 . 23 -
' 2NW1458 CN-2569-1.0 C05 2 B ACT Gate SO ST/FT-Q Pt 23 4
2NW147 CN-2569-1.0 J07 2 C ACT Check SA FSOC-Q CN-NW-02 ' 23 Secte 4.2 NW - 2 of 4 Rev.23 06/29/96
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O 9 Unit 2- Catawba Nuclear Station Inservice Testing Program TEST TEST FLOW FLOW ASME VALVE ACT ACT~ REQwT MQwT JUSTIF FOR TEST VALVE NUMSER DLAGRAM COOR CLAS$ CATORY PAS VALVE TYPE TYPE NO.1 NO. 2 REUEF REOST DEFERRAL RBMWOLS . ALTERNATIVES REV CONTAINMENT PENETRATION VALVE INJECTION WATER SYSTEM (NW) ~ 2NW1'48 - CN-2569-1.0 J07 2 C ACT Check SA FSCWC-Q CN-NW-02 23 . 2NW159 CN-2569-1.0 ~ 11 2 2- C ACT Check SA FSO/C-Q CN-NW-02 23 2NW160 CN-2569-1.0 J12 2 C ACT Check SA FSO/C-Q CN-NW 23 ' 2NW163 ^ CN-2569-1.0 K12 2 C ACT Check SA FSO/C-Q CN-NW-02 23 ~ , 2NW164 CN-2569-1.0 K12 2 C ACT Check SA FSO/C-Q CN-NW-02 23 - 2NW168 CN-2569-1.0 K13 2 C ACT Check SA FSO/C-Q CN-NW-02 23 , 2NW169 CN-2569-1.0 K13 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW171 CN-2569-1.0 J13 '2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW172 CN-2569-1.0 'J13 2 C ACT Check SA FSO/C-Q CN-NW-02 . 23' 2NW175A CN-2569-1.0 C12 2 B ACT Gate SO ST/FT-Q Pt 23 - 2NW178 CN-2569-1.0 C12 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW179 CN-2569-1.0 C12 2 C ACT Check SA FSO/C-Q CN-NW 23 2NW180A CN-2569-1.0 C13 2 B ACT Gate SO ST/FT-Q PI 23 _ 2NWi83 CN-2569-1.0 C13 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW184 CN-2569-1.0 C13 2 C ACT Check SA FSO/C-Q CN-NW-02 23-2NW185A CN-2569-1.0 C13 2 B ACT Gate SO ST/FT-Q PI 23
- 2NW188 CN-2569-1.0 C13 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW189 CN-2569-1.0 C13 2 C ACT Check SA FSO/C-Q CN-NW-02 23 t 2NW190A CN-2569-1.0 C14 2 B ACT Gate SO ST/FT-Q PI 23 4
2NW193 ' CN-2569-1.0 C14 2 C ACT Check SA FSO/C-Q CN-NW-02 23
- 2NW194 CN-2569-1.0 C14 2 C ACT Check SA FSO/C-Q CN-NW-02 23-2NW195A CN-2569-1.0 E08 2 B ACT Gate SO ST/FT-Q Pl 23 2NW196 CN-2569-1.0 F08 2 C ACT Check SA FSO/C-Q CN-NW-02 23-2NW197 CN-2569-1.0 F08 2 C ACT Check SA FSO/C-Q CN-NW-02 23 1 2NW200A CN-2569-1.0 E08 2 B ACT Gate SO ST/FT-Q Pt 23 ;
2NW201 CN-2569-1.0 E08 2 C ACT Check SA FSO/C-Q CN-NW 23 ; 2NW202 CN-2569-1.0 D08 2 C ACT Check SA FSO/C-Q CN-NW-02 23- ; 2NW205 CN-2569-1.0 F07 2 C ACT Check SA FSO/C-Q CN-NW-02 23 Section 4.2 NW - 3 of 4 Rev. 23 06/29/96
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O r Unit 2- Catawba Nuclear Station l Inservice Testing Program ; TEST TEST ASME VALVE ACT .ACT REOWT REQ wT JUST1F FOR ' . TEST PLOW FLOW VALVE esuMBER DIAGRAM COOR CLASS CATORY PAS VALVE TYPE TYPE 10 0 .1 NO. 2 REUEF REOST DEF9WIAL rem 4Afuts -- ' ALTWINA11VES . REV . CONTAINMENT PENETRATION VALVE INJECTION WATER SYSTEM (NW) l- SA FSOC-Q CN-NW-02 23 2NW206 CN-2569-1.0 F07 2 C ACT Check CN-2569-1.0 E07 2 C ACT Check SA FSOC-Q CN-NW-02 23 2NW209 2NW210 CN-2569-1.0 E07 2 C ACT Check SA FSOC-Q CN-NW-02 23 2NW213 CN-2569-1.0 C07 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW214 CN-2569-1.0 C07 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW217B - CN-2569-1.0 C08 2 B ACT Gate SO ST/FT-Q PI '23
- 2NW218 CN-2569-1.0 C08 2 C ACT Check SA FSOC-Q CN-NW-02 23 '
2NW219 CN-2569-1.0 C08 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW222B CN-2569-1.0 C09 2 B ACT Gate SO ST/FT-Q PI 23 2NW223 CN-2569-1.0 C09 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW224 CN-2569-1.0 C09 2 C ACT Check SA FSO/C-Q CN-NW-02 23 f 2NW227B CN-2569-1.0 C09 2 B ACT Gate SO ST/FT-Q Pl 23 - 2NW230 CN-2569-1.0 C09 2 C ACT Check SA FSO/C-Q CN-PAV-02 23-2NW231 CN-2569-1.0 C09 2 C ACT Check SA FSOC-Q CN-NW-02 23' 2NW2328 CN-2569-1.0 C10 2 B ACT Gate SO ST/FT-Q Pt 23 2NW235 CN-2569-1.0 C10 2 C ACT ' Check SA FSO/C-Q CN-NW-02 23 2NW236 CN-2569-1.0 C10 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW237B CN-2569-1.0 C11 2 B ACT Gate SO ST/FT-Q PI 23 2NW240 CN-2569-1.0 C11 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW241 CN-2569-1.0 C11 2 C ACT Check SA FSO/C-Q CN-NW-02 23- i 2NW2428 CN-2569-1.0 C11 2 B ACT Gate SO ST/FT-Q Pl .23 2NW245 CN-2569-1.0 C11 2 C ACT Check SA FSO/C-Q CN-NW-02 23 2NW246 CN-2569-1.0 C11 2 C ACT Check SA FSO/C-Q Cl4-NW-02 23 2NW247 CN-2569-1.0 J11 2 C PAS Relief SA RV 150 PSIG 23 2NW248 CN-2569-1.0 D11 2 C PAS Relief SA RV 150 PSIG ' 23 2NW249 CN-2569-1.0 DOS 2 C PAS Relief SA RV 150 PSIG 23 Section 4.2 NW- 4 of 4 Rev. 23 06/29/96
1 e. O O O Unit 2- Catawba Nuclear Station , inservice Teshng Program , 1 TEST TEST - ACT stEOMT JtJSTIF FOR , TEST . FLOW FLOW ASME VALVE ACT - ftEQui . ALTEppsAftvES MEV DIAeRAM COOR CLASS CATORY PAS VALVE TYPE TYPE BeO.1 NO. 2 - HELIEF REOST DEFEButAL neMARKS VALVE NUMSER FIRE PROTECTION SYSTEM (RF) CN-1599-2.1 E01 2 A ACT Gate MO ST-Q Pt 23
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-2RF392 CN-1599-2.1 E03 2 AlC ACT Check SA ' FSOtC-Q -U- .CN4tF-01 '.
CN-1599-2.1 G04 2 'A ACT Gate MO ST-Q Pi 23 2RF447B CN-1599-2.1 G07 2 A/C ACT Check SA FSO/C-Q U CN-RF - 23 ' 2RF448 CN-1599-2.1 G03 2 B ACT Gate MO ST-Q Pi 23 2RF457B I
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Section 4.2 RF- 1 of 1 Rev.23 06/29/96
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k Unit 2- Catawba Nuclear Staten 4 Insennce Testmg Program q TEST TEST FLOW - FLOW ASAME VALVE ACT ACT NEOMT .. REQWT . JUSTIF FOR TEST + i VALVE NutsBER DIAGRARE COOR CLASS CATGRY PAS VALVE TYPE TYPE NO1 NO 2 . HELIEF REQST ~ DEFEfutAL REthAAKS : ALTEfulmTNES MEV -- a NUCLEAR SAarLING WATER SYSTERA (RN) i
- 2RN009 CN-1574-1.0 EE11 3 C '
ACT Check SA FSOdC-Q ' 23 "I
. 2RN011 A : CN-1574-1.0 ' E09 3 B 'ACT ; ban MO ST-Q P1 423:
- 2RN018 CN-1574-12 F13 3 C ACT Check 'SA FSO/C-Q ' 23 .j 2RN0208 CN-1574-12 E11 3 B ACT Ball MO ST-Q P1 23j 2RN028A . CN-1574-1.0 E11 3 B ACT Butter 9y MO ST-Q PI 23~
2RNO38B CN-1574-1.2 F13 3 B ACT BumerSy MO ST-Q - Pt ;23 .; 2RN047A CN-1574-1.1 H10 3 B ACT Butterey MO ST-Q Pl 23 j ' 2RN0488 . CN-1574-1.1 H12 3 B ACT Butterey MO ST-Q PI '23i 2RN049A CN-1574-1.1 G11 3 B ACT Butter 9y MO ST-Q . Pt 23; .f
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c 2RN050B CN-157'4-1.1 G11 3 B ACT Butter 9y MO ST-Q PI - 23
. 2RN051 A _ CN-1574-1.1 C08 3 B ACT. Butter 9y MO ST-Q Pi' 23 2RN0528 CN-1574-1.1 C08 3 -B ACT Butter 9y MO ST-Q PI .23 l!
2RN144A CN-2574-2.0 - C05 3 B ACT Buner9y MO ' ST-Q PI '23: 3 ACT l 2RN148A CN-2574-2.0 - LO1 B Butter 9y MO ST-Q Pt 73 2RN2258 CN-2574-2.4 C06 3 8 ACT Butter 9y MO ST-Q Pt 23 [ 2RN2298 . CN-2574-2.4 LO7 3 B ACT Butte:9y MO . ST-Q Pt 23 2RN232A CN-2574-2.1 D02 3 B ACT Butter 9y MO ST-Q - Pi - 23 _; l 2RN250A CN-2574-2.1 ' C07 3 B ACT Gate MO ST-Q Pt 23 j 2RN291 CN-2574-2.1 J13 3 B ACT' ban AO ST/FT-Q Pl 23 I
- 2RN2928 CN-2574-2.5 E02 3 B ACT Butter #y MO ST-Q PI - 23 j.
2RN3108 - CN-2574-2.5 E06 3 B ACT Gate MO ST-Q PI 23 ' ! 2RN351 CN-2574-2.5 11 3 3 B ACT Ball AO ST/FT-Q Pi - 23 4 2RN4048 CN-2574-2.7 D04 2 B ACT Gate MO ST-Q PI 23 l I-2RN405 CN-2574-2.7 E03 2 A/C ACT Check SA FSO/C-Q LJ CN-RN-01 23: l 2RN430 CN-2574-2.2 803 2 A/C ACT Check SA FSC-Q LI 23
'2RN437B ~ CN-2574-2.2 LO6 2 B -ACT Gate MO ST-Q Pi CN-RN-02 23 2RN438 CN-7574-2.2 LOS 2 A/C ACT Check SA FSO/C-Q - LJ CN-RN-01 23 Section 4 2 RN - 1 of 2 -
Rev. 23 06/29/96 ~ f f l.- _..n.
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Unit 2 -Catawba Nuclear Staton Inservice Testing Program TEST TEST FLOW FLOW ASME VALVE ACT ACT REQwT REQwT JUSTIF FOR TEST VALVE 9suMBER DIAGRAM COOR CLASS CATGRY PAS VALVE TYPE TYPE No1 Is0 2 REUEF REQST DEFERRAL REMARKS ALTEReRThES . REV NUCLEAR SAMPUNG WATER SYSTEM (RN) 2RN484A CN-2574-2.2 COB 2 B ACT Gate MO ST-Q PI CN-RN-03 ~23 2RN485 CN-2574-2.2 B08 2 AIC ACT Check SA FSC-Q LJ 23 2RN487B CN-2574-2.2 C07 2 B ACT Gate MO ST-Q Pi CN-RN 23
~ 2RN846A CN-2574-2.1 J02 3 B ACT Buttedly MO ST-Q PI 23 2RN847A CN-2574-2.1 J01 3 B ACT Butterfly MO ST-Q Pl . 23 CN-2574-2.5 J02 3 B ACT Butterfly MO PI l 2RN8488 ST-Q 23 2RN8498 CN-2574-2.5 J02 3 B ACT Butterfly MO ST-Q Pl 23 2RN854 CN-2574-1.0 F12 3 C ACT Relief SA RV -0.2 PSIG 23' '
2RN855 CN-2574-1.0 F03 3 C ACT Relief SA RV -0.2 PSIG 23-4
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I Section 4.2 RN - 2 of 2 Rev. 23 06/29/96 i i
C O O Unit 2- Catawba Nuclear Station Inservice Test'mg Pmgram TEST TEST FLOW Asamt VALVE ACT ACT REQ WT REQ wT JUSTW FOR TEST FLOW VALVENuessER ORAGRAM COOR CLASS CATGRY PAS VALVE TYPE TYPE 90 0 .1 f60. 2 REUEF REOST DEFENtAL RSAAHKs ' ALTEmeAftWS REV MAIN STEAM TO AUX EQUIPMENT (SA) 2SA002 CN-2593-1.1 G04 2 B ACT Gate AO ST/FT-Q Pt 23 2SA003 CN-2593-1.1 GOS 2- C ACT Check SA FSO/C-Q CN-SA-01 23
-2SA005 CN-2593-1.1 H04 2 B ACT Gate AO ST/FT-Q Pt 23 2SA006 CN-2593-1.1 HOS 2 C ACT Check SA FSO/C-Q CN-SA-01 23 -
i i I I l i Section 4.2 SA - 1 of 1 Rev. 23 06/29/96
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O O O , Unit 2 - Catawba Nuclear Station Inservice Testing Program . TE57 TEST ASME VALVE ACT ACT REQ WT REQ WT JUSTW FOR TEST FLOW FLOW DIAGRAM COOR CLASS CATGRY PAS VALVE TYPE TYPE No.1 90 0 . 2 REUEF REQST DEFERRAL REMMES . ALTERNATIVES REV
' VALVE aruusER MAIN STEAM (SM)
' 2SM001 CN-2593-1.0 K13 2 B ACT Globe AO ST/FT-Q Pl CN-SM-01 23 2SM003 CN-2593-1.0 H13 2 B ACT Globe AO ST/FT-Q Pi CN-SM-01 23 2SM005 CN-2593-1.0 F13 2 B ACT Globe AO ST/FT-Q Pi CN-SM-01 23 I-2SM007 CN-2593-1.0 C13 2 B ACT Globe AO ST/FT-Q Pl CN-SM-01 23 2SM009 CN-2593-1.0 J13 2 B ACT Globe AO ST/FT-Q Pt 23 2SM010 CN-2593-1.0 G13 2 B ACT Globe AO ST/FT-Q Pl 23 2SM011 CN-2593-1.0 E13 2 B ACT Globe AO ST/FT-Q Pl 23
.2SM012 CN-2593-1.0 B13 2 B ACT Globe AO ST/FT-Q Pl 23 ;
t L 4 Section 4.2 SM - 1 of 1 Rev. 23 06/29/96
l l l O O O Unit 2 - Catawba Nuclear Station laservice Testing Program l TEST TEST ASME VALVE ACT ACT MQWT MQ'MT JUSTtF FOR TEST Flow FLOW COOR CLASS CATORY PAS VALVE TYPE TYPE NO.1 NO. 2 RELIEF REQST DEFEfmAL REMARKS - ALTERNATIVES MV l VALVE huMMR DeAGRAM MAIN STEAM TO ATMOSPHERE (SV) 2SV001 CN-2593-1.0 K12 2 B ACT Globe AO ST/FT-Q PI 23 2SV002 CN-2593-1.0 K04 2 C ACT Relief SA RV 1175 PSIG 23 2SV003 CN-2593-1.0 KOS 2 C ACT Relief SA RV 1190 PSIG 23 2SV004 CN-2593-1.0 K07 2 C ACT Relief SA RV 1205 PSIG 23 2SV005 CN-2593-1.0 K08 2 C ACT Relief SA RV 1220 PSIG 23 2SV006 CN-2593-1.0 K10 2 C ACT Relief SA RV 1230 PSIG 23 2SV007 CN-2593-1.0 11 2 2 B ACT. Globe AO ST/FT-Q PI 23 2SV008 CN-2593-1.0 10 4 2 C ACT Relief SA RV 1175 PSIG 23 2SV009 CN-2593-1.0 105 2 C ACT Relief AO RV 1190 PSIG 23 , 2SV010 CN-2593-1.0 10 7 2 C ACT Relief AO RV 1205 PSIG 23 2SV011 CN-2593-1.0 10 8 2 C ACT Relief AO RV 1220 PSIG 23 2SV012 CN-2593-1.0 11 0 2 C ACT Relief AO RV 1230 PSIG 23 2SV013 CN-2593-1.0 F12 2 B ACT Globe AO ST/FT-Q PI 23 2SV014 CN-2593-1.0 F04 2 C ACT Relief SA RV 1175 PSIG 23
- 2SV015 CN-2593-1.0 F05 2 C ACT Relief SA RV -
1190 PSIG 23 2SV016 CN-2593-1.0 F07 2 C ACT Relief SA RV 1205 PSIG 23 2SV017 CN-2593-1.0 F08 2 C ACT Relief SA RV 1220 PSIG 23 2SV018 CN-2593-1.0 F10 2 C ACT Relief SA RV 1230 PSIG 23 l 2SV019 CN-2593-1.0 D12 2 B ACT Globe AO ST/FT-Q PI 23
'2SV020 CN-2593-1.0 C04 2 C ACT Relief SA RV 1175 PSIG 23 ,
2SV021 CN-2593-1.0 C05 2 C ACT Relief SA RV 1190 PSIG 23 , 2SV022 CN-2593-1.0 C07 2 C ACT Relief SA RV 1205 PSIG 23 l 2SV023 CN-2593-1.0 C08 2 C ACT Relief SA RV 1220 PSIG 23 , 2SV024 CN-2593-1.0 C10 2 C ACT Relief SA RV 1230 PSIG 23 2SV025B CN-2593-1.0 K11 2 B ACT Gate MO. ST-Q PI 23 2SV0260 CN-2593-1.0 11 1 2 B ACT Gate MO ST-Q Pl 23 [ 2SV027A CN-2593-1.0 C11 2 B ACT Gate MO ST-Q PI 23 2SV028A CN-2593-1.0 F11 2 B ACT Gate MO ST-Q PI 23 r Section 4.2 SV-1of1 Rev. 23 06/29/96 f
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Unit 2- Catawba Nuclear Station Inservice Testing Program
. TEST TEST .
-PLOW ASME v4VE ACT ACT REQWT REQ wT JUETIF FOR . TEST FLOW DEAGRAM COOR MASS CATGRY PAS VALVE TYPE -TYPE - No.1 00 0 . 2 REUEFREQST DEF5WlAL REMARKS ^ ALYWWIATWES REV VALVE IsunseeR BREATHING AIR SYSTEM (VB) 2VB0638 CN-2605-3.2 10 7 2 A ACT Diaphram MO ST-Q LJ/PI 23 2VB065 CN-2605-3.2 H07 2 A/C ACT Check SA FSO/C-Q LJ CN-VB-01 23 i
Section 4.2 VB - 1 of 1 ' Rev.23 06/29/96 _ _ _ _ _ _ - _ - - - _ _ _ _ _ - _ _ - _ _ _ _ = _______ _ . _ _. _ _ _ - - _ _ .-. - ,. - . . . .
Unit 2- Catawba Nuclear Station Insennce Testing Program ,
-TEST - TEST FLOW FLOW ASAsf VALVE ACT ACT' nEQwT flEOMT JUST1F FOR -TEST DeMBRADA COOR CLASS CATORY PAS VALVE TYPE TYPE 80 0 .1 1e0. 2 REUEF flEOST DEF5WIAL IWhaAftLS ALTEpueATIVES REV VALVE leUhASER DOESEL GENERATOR ENGINE STARTING AIR (VG) 2VG005 CN-2609-4.0 10 2 3 C ACT Check SA : FSC-Q 23 2VG006 CN-2609-4.0 11 3 3 C ACT Check SA FSC-Q 23 2VG007 CN-2609-4.0 10 2 3 C ACT Check SA- FSC-Q 23 2VG008 CN-2609-4.0 11 3 3 C ACT Check SA FSC-Q 23
'2VG015 CN-2609-4.0 G02 3 C ACT Check SA FSOtC-Q CN-VG-01 23 2VG016 CN-2609-4.0 G13 3 C ACT Check SA FSO/C-Q CN-VG-01 23 2VG025 CN-2609-4.0 DOS 3 B ACT Gate SO ST-Q Pl Ctv-VG42 23 2VG026 CN-2609-4.0 D10 3 B ACT Gate SO ST-Q Pi CN-VG-02 23 .
2VG027 CN-2609-4.0 C05 .3 B ACT Gate SO ST-Q Pi CN-VG42 ' 23
- 2VG028 CN-2609-4.0 C10 3 B ACT Gate SO ST-Q Pl CN-VG-02 23 2VG029 CN-2609-4.0 D06 3 C ACT Check SA FSOlC-Q CN-VG-01 23-23-2VG030 CN-2609-4.0 D10 3 C ACT Check SA FSO/C-Q CN-VG-01 2VG031 CN-2609-4.0 C05 3 C ACT Check SA FSO/C-Q CN-VG-01 23'
- 2VG032 CN-2609-4.0 C10 3 C ACT Check SA FSOtC-Q CN-VG-01 ' 23 2VG049 CN-2609-4.1 10 2 3 C ACT Check SA FSC-Q 23 2VG050 CN-2609-4.1 11 3 3 C ACT Check SA FSC-Q 23
' 2VG051 CN-2609-4.1 J02 3 C ACT Check SA FSC-Q 23 2VG052 CN-2609-4.1 J13 3 C ACT Check SA FSC-Q 23 2VG059 CN-2609-4.1 G02 3 C ACT Check SA FSO/C-Q CN-VG-01 23 2VG060 CN-2609-4.1 G13 3 C ACT Check SA FSOtC-Q . CN-VG-01 23 .i 2VG069 CN-2609-4.1 DOS 3 B ACT Gate SO ST-Q Pl CN-VG-02 23-2VG070 CN-2609-4.1 D10 3 B ACT Gate SO ST-Q Pl CN-VG-02 23
- 2VG071 CN-2609-4.1 COS 3 B ACT Gate SO ST-Q Pi CN-VG-02 23 ,
l 2VG072 CN-2609-4.1 C10 3 B ACT Gate SO - ST-Q Pl CN-VG-02 23 2VG073 CN-2609-4.1 DOS 3 C ACT Check .SA - FSO/C-Q CN-VG-01 23 : 2VG074 CN-2609-4.1 D10 3 C ACT Check SA FSO/C-Q CN-VG-01 23 '! 2VG075 CN-2609-4.1 C05 3 C ACT Check SA FSOtC-Q CN-VG-01 -23 2VG076 ' CN-2609-4.1 C10 3 C ACT Check SA FSOtC-Q CN-VG-01 23 ; Section 4.2 VG - 1 of 2 - .y Rev. 23 06/29/96 ; l _ _ _ _ _ _ _ _ ~ _ _ _ _ _ _ . __- -_- __ _ _ _ _ _ . _ _ - _ _ _ - _ . _ _ _ - _ . _ _ = _ _ _ _ _ _ _ _ _ . _
Unit 2- Catawba Nuclear Station Insennce Testing Program TEST TEST FLON ROW ASME VMYE AcT ACT nEQWT nEQwf JUSTIF Fon TEST vavE muusen -- coon ctass cafony cAs vnvE Tm Tm mo.s no. 2 neuEF nEast oEFenna nowms mienmatus nEv l DIESEL GENERATOR ENGINE STARTING AIR (VG) 2VG1'33 CN-2609 4.1 H02 3 C ACT Check SA FSO/C-Q 23 l 2VG134 CN-2609-4.1 H13 3- C ACT Check SA FSO/C-Q 23 - 2VG135 CN-260lM.0 H02 3 C ACT Check SA- FSOIC-Q 23-2VG136 CN-260lM.0 H13 3 C ACT- Check SA FSO/C-Q 23 Section 4.2 VG - 2 of 2 Rev. 23 06/29/96
D c C Unit 2- Catawba Nudear Station Inservce Testing Program TEST TEST . FLOW FLOW ASME VALVE ACT ACT MQwT MQWT JUSTIF K R TEST VALVENuesMR DIAGRAM COOR CLASS CATORY PAS VALVE TYPE 1YPE- MO3 NO. 2 RELSEF REOST DEFERRAL MhAAfuts ALTsusAftvES MV INSTRUMENT AIR SYSTEM (VI) 2Vl077B CN-2605-1.5 10 5 2 A ACT Diaphram MO ST-Q LJ/PI CN-VI-02 23 2Vl079 ' CN-2605-1.5 10 8 2 A/C ACT Check SA FSCVC-Q U CN-VI-01 23. 2Vl312A CN-2605-1.5 10 6 2 A ACT Globe MO ST-Q U/PI 23 2Vl367 CN-2605-1.5 E09 - C ACT Check SA FSO/C-Q CN-VI-03 23 2Vl368 CN-2605-1.5 F09 - C ACT Check SA FSO/C-Q CN-VI-03 23 - 2Vl369 CN-2605-1.5 E08 - C ACT Check SA FSO-Q CN-VI-04 23 2Vl370 CN-2605-1.5 F08 - C ACT Check SA FSO-Q CN-VI-04 23 Section 4.2 VI- 1 of 1 Rev.23 06/29/96 -
- . , - - . . -- , , - ~ , ,Q
. r ~s ( m Unit 2- Catawba Nuclear Station Inservice Testing Program TEST TEST FLOW FLOW ASME VALVE ACT ACT MQ"MT MQwT JusTtF FOR - TCST VALVE NUMsER DIAGRAM COOR class CATORY PAS VALVE TYFE TYPE NO.1 NO. 2 REUEF MOST - DEFERRAL REMAfES ALTEIU$ATWES MV CONTAINMENT PURGE VENTILATION SYSTEM (VP) l .
2VP001B CN-2576-1.0 10 5 2 A PAS Butterily AO LJ/PI 23 2VP002A CN-2576-1.0 10 6 2 A PAS . Butterfly AO LJ/PI 23 2VP003B CN-2576-1.0 H05 2 A PAS Butterfly AO LJ/Pt 23-2VP004A CN-2576-1.0 H06 2 A PAS Butterfly AO LJ/PI 23 2VP006B CN-2576-1.0 GOS 2 A PAS Butterfly AO LJ/PI 23 2VP007A CN-2576-1.0 G06 2 A PAS Butterfly AO Ll/PI 23 2VP0088 CN-2576-1.0 F05 2 A PAS Butterfly AO Ll/PI 23-2VP009A CN-2576-1.0 F06 2 A PAS Butterfly AO LJ/PI 23 2VP010A CN-2576-1.0 109 2 A PAS Butterfly AO LJ/PI 23 2VP011B CN-2576-1.0 11 0 2 A PAS Butterfly AO Ll/PI 23 2VP012A CN-2576-1.0 H09 2 A PAS Butterity AO LJ/PI - 23 2VP0138 CN-2576-1.0 H10 2 A PAS Butterfly AO LJ/PI 23
-2VP015A CN-2576-1.0 F09 2 A PAS Butterfly AO . LJ/PI 23 2VP016B CN-2576-1.0 F10 2 A PAS Butterfly AO LJ/P1 23 2VP017A CN-2576-1.0 E09 2 A PAS Butterfly AO LJ/PI -
23 2VP0188 CN-2576-1.0 E10 2 A PAS Butterfly AO LJ/PI 23 2VP019A CN-2576-1.0 E06 2 A PAS Butterfly AO LJ/PI 23 2VP0208 CN-2576-1.0 EOS 2 A PAS Butterfly AO LJ/Pl 23 , i SectV 4.2 VP - 1 of 1 j Ret J 06/29/96 '
.. ~_ . - . .. . .. . - . - - . . - . - ....
m
~
( b l Unit 2- Catawba Nuclear Station Insennce Testing Program TEST TEST AsME VALVE ACT ACT MQ'MT REQ WT JUSTIF FOR TEST FLOW FLOW COOR class CATORY PAS VALVE TYPE TYPE NO.1 NO. 2 REUEFREOST DEF9 MAL REMARKS ALTHWeATIVES REV VALVE NUMSER OLAGRAM CONTAINMENT AIR RELEASE & ADDITION SYSTEM (VQ)
- 2VQ002A CN-2585-1.0 10 2 2 A ACT DW MO ST-Q LVPI 23 CN-2585-1.0 G02 2 A ACT Gate MO ST-Q LJ/Pt 23 2VQ0038 '
CN-2585-1.0 2 A ACT Gate MO ST-Q LJ/PI 23 , 4 2VQO15B 11 2 2VQO16A CN-2585-1.0 J12 2 A ACT Diaphram MO ST-Q LJ/PI 23 l 2 3 r & 4 i 4 f ( i t I t i Section 4.2 VQ - 1 of 1 Rev. 23 06/29/96 i i
. ..s
. - . . _ . _ - . _ . . _ . , . ~ . _ . . - _ . _ . - _ . _ _ _ ._ ._ .m f ; Unit 2 - Catawba Nuclear Station .
Inseo/ ice Testing Program TEST TEST Flow ASAst VALVE ACT ACT REQWT REQ wT JusTIF FOR TEST , FLOW coOR CLASS CATORY PAS VALVE TYPE TYPE NO.1 NO. 2 REufF REOST DEFe MAL REtsApets ALTUWeAtiVES ' REV VALVE NummeER DIAeRame i I 6 STATION AIR SYSTEM (VS) 2VS0548 CN-1605-2.1 GOS 2 A ACT Gate MO ST-Q LT/Pt 23 2VS056 CN '605-2.1 G03 2 AIC ACT Check SA FSO/C-Q U CN-VS-01 .23 :t 1 i-I 1 , i h i I I l t i t i
^
i Section 4.2 VS-1of1 ' Rev.23 06/29/96
O Unit 2- Catawba Nuclear Station Inservice Testing Program TEST TEST-PLOW FLOW ASME VALVE ACT ACT REQWT REQWT JusTIF FOR ' TEST . > VALVEIsUMBER ' DeAGRAM COOR CLASS CATORY PAS VALVE TYPE TYPE seO 1 NO. 2 . ftEUEF REost DEFWuuL REMARKS ALTsueATIVEs REV
. CONT. AIR RET. & HYDROGEN SKIMMER SYSTEM (VX) 2VX001A CN-2557-1.0 G03 2, B ACT Butterfly MO ST-Q Pt 23.
2VX0028 CN-2557-1.0 G14 2' B ACT Butterfly MO ST-Q Pl 23 i i I l l' I i section 4.2 VX - 1 of 1 Rev.23 06/29/96
. _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ , _ _ . _- _ _ _ _ _ , . ~ __
* ~
O v Unit 2- Catawba Nuclear Station . Inservice Testing Program TEST TEST PLOW FLOW ASeat VALVE ACT ACT REQWT REQwT JUSTIF POR TEST VALVE teURASSL DIAGRAAA COOft CLASS CATORY PAS VALVE TYPE TYPE Iso.1 80 0 . 2 REutF ftEOsf DEFUutAL RERAARKS ALTsueATIVES . REV CONTIANMENT HYDROGEN SAMPLE & PURGE SYSTEM (W)
- 2WO15B CN-2559-1.0 - F07 2 A PAS Gate MO U PI 23 I
2WO16 CN-2559-1.0 D07 2 NC ACT Check SA FSO/C-Q U CN-W-01 23 2WO17A CN-2559-1.0 D04 2 A FAS Gate MO U- PI 23 -
' 2WO188 CN-2559-1.0 G04 2 A PAS Gate MO U Pi 23~
i 1 4 yy - 1 of 1 , Section 4.2 Rev. 23 06/29/96
m _. . . _. _ __._. . .m_.___ _ . . - . .. .__. .m .. .. _ _. -.. i Unit 2- Catawba Nuclear Station inserwoe Testing Program
. TEST TEST JUS 7FFOR- TEST PLOW PLOW Aftet VALVE ACT ACT HEQ1MT ftEQWT . .
TYPE Iso.1 flEUEF REOST DEFEfWIAL I4'tBAfutS ALTsueATTVES stEV .
' VALyt seURASER DIAGRAM COOR CLmSS CATORY PAS VALVE TYPE 80 0 . 2 EQUIPMENT DECONTAINGRENT SYSTEM (WE)
Globe MA U ..23 2WE020 CN-2568-1.0 J07 2 A PAS A PAS Globe MA U 23
- 2WE022 - CN-2568-1.0 H07 2 t
1 WE - 1 of 1 Sedion 4.2 Rev.23 06/29/96 ' ,m . .- . _ _ . _ m._ m. . _ ... _ _ _ . _ . _ _ _ . _ -_ _ ._m______- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ . __.__ ________m__ _ _ _
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Unit 2- Catawba Nuclear Station Inservice Testing Program TEST TEST ROW FLOW ASME VALVE ACT ACT REQWT REQWT JUSTIF FOR TEST-VALVE NUMSER DEAGRAM COOR class CATGRY~ PAS VALVE TYPE TYFE NO.1 NO. 2 REUEF REQST . DEFERRAL REMARKS ALTERNATIVES REV LIQUID WASTE RECYCLE SYSTEM (WL) 2WL321 CN-2565-2.4 H06 2 A/C ACT Check SA FSC-Q U 23 2WL450A CN-2565-2.0 10 4 2 A ACT Globe MO ST-Q ' LJ/PI 23 2WL4518 CN-2565-2.0 J04 2 A ACT Globe MO ST-Q U/PI 23 2 A ACT Gate MO ST-Q U/PI r; 2WL805A CN-2565-2.0 10 8 2WL806 CN-2565-2.0 108 2 A/C ACT Check SA FSC-Q LJ 23 . 2WL807B CN-2565-2.0 . J08 2 A ACT Gate MO ST-Q U/Pt -23 2WL825A CN-2565-2.4 H07 2 A ACT Gate MO ST-Q U/Pi 23 2WL827B CN-2565-2.4 J07 2 A. ACT Gate MO ST-Q LJ/PI 23 2WL830 CN-2565-2.2 D08 3 C ACT Check SA FSO/C-Q - 23 2WL832 CN-2565-2.2 D10 3 C ACT Check SA FSO/C-Q 23 2WL867A CN-2565-2.1 10 7 2 A ACT Gate MO ST-Q - U/PI 23 2WL868 CN-2565-2.1 10 6 2 A/C ACT Check SA FSC-Q LJ 23 2WL869B CN-2565-2.1 H07 2 A ACT Gate MO- ST-Q U/PI 23 2WLA022 CN-2565-2.6 H10 2 A/C ACT Check SA FSC-Q LJ 23 Section 4.2 WL- 1 of 1 Rev. 23 06/29/96
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d Y Unit 2-Catawba Nuclear Station Inservice Testing Program TEST TEST ACT REQwT REO WT JusTIF FoR TEST Flow FLOW ASME VALVE ACT pas vALvt Type Yvet no.i no, a RELIEF REOST DEFERRAL REleAfuts ' ALTERNATIVES REV ' vAtw muusen owuuma cooR ctAss cAToRv i MAKEUP DEMINERAI 17FR WATER SYSTEM (YM) 2 A ACT Globe MO ST-Q LJ/Pt 23 2YM119B CN-1601-3.1 EOS E11 2 A/C ACT Check SA FSO/C-Q LJ - CN-YM 23 j 2YM121 CN-1601-3.1 i i k I i i t i L Section 4.2 YM - 1 of 1 Rev. 23 06/29/96
l l l( i 4 CATAWBA NUCLEAR STATION i f i. i 1 I 4 i RELIEF REQUEST iO 4 seceon 5.0 l i j a t j
- O l
1
l i
- 5.1 PUMP GENERIC RELIEF REOUESTS l
ReliefRequest Applic5>ility Status 1 None i 1 I I 1 I l 1 I l i i ( 2 t J l a l l i Rev.23 Page1of I l l 1
1 2 h i 5.2 PUMP SPECIFIC RELIEF REOUESTS 1 1 RelidRequest Appbcabdity Status i l CN-SRP-CA 01 Auxahary FeedwaterPumps Revised 06/29/96 1 1 l 2 l 1 I 4 ,4 i 1 1 i I i ( i l 1 i i b 4 i 1 i i i I i i 7 f 1 1 4 t
- i. <
4 S. Rev.23 , Page1of I i-o
i l l Ccttwba Units 1 cnd 2 l O l Specific Relief Reauest item Number: CN-SRP-CA-01 l I Pump: CA Pump 1A, CA Pump IB, CA Pump 2A, CA Pump 2B, Test Requirement: Oma 1988, Part 6, Section 4.6.1.2.a requires that the full scale range I of the instrument shall be three times the reference value or less. Basis for Relief: The installed process instrumentation for the CA pumps suction pressure measurement is as follows: Pump Local Control Room 1A/2A 0-160 psig (0.5% error) 0-90 psig (1.12% error) IB/2B >160 psig (0.5% error) 0-90 psig (1.12% error) (TN Q The typical range of values for the suction pressure of the CA pumps during testing is 33-38 psig; therefore, the local process I instrumentation on CA Pumps IA/2A and IB/2B does not meet the , I three times criteria. The accuracy of the process instrumentation (0.5%) is well below the requirements specified in Oma-1988 Part 6, l Table I for pressure instrumentation accuracy (2.0%). The actual reading error at test pressure due to the process instrumentation j accuracy is 2.42% (0.5%
- 160/33). If a 0-90 psig test instrument is I
used (which meets the three times criteria) and k has an accuracy of 2.0%, then the reading error due to instrument accuracy would be 5.45% (2%
- 90/33). When the requirements of Oma-1988 Part 6, Section 4.6.1.2.a and Tnble 1 are combined, the actud instrument error introduced to the test is less than the code allowable (2.42% vs.
5.45%)~ Using the process instrument for suction pressure data does not degrade the quality of the test, and meets the intent of the instrumentation requirements of the code. i Test Alternative: The installed process instrumentation at both the control room and locally at the CA pumps can be used to measure CA pump suction pressure for CA Pump 1 A, CA Pump IB, CA Pump 2A, and CA Pump 2B tests. v 06/29/96 CN-SRP-CA-01 Rev.23 Page1 of I Section 5.2
4 4 .; 5.3 VALVE GENERIC RELEF REOUESTS .
. ReliefRequest Applicability Status j Wie 4
.1 4 d
'f d
4 l O ! l 3 4 i i i i 1 i e 1 O 1 Rev.23 Page1of I l l
p 5.4 VALVE SPECIFIC RELIEF REOUESTS us
- WRaque Appixhlity Smus None k
I i i
?
l 1 1, 4 b +. 4 i. I i i i- ; 1 1 Rev.23 3 Page1 of 1 [ i
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1 O CATAWBA NUCLEAR STATION 1 i .i . I i ) 1 i JUSTIFICATION FOR DEFERRAL !O section 6.0 i I 1. i l I 3 1 l 1 l i o l d i
!O
_ _ _ _ _ _-___ m ._ _ _ ____ __-_u _ . - - - - - - _ -- - , - - - , ,
6.1 VALVE JUSTIFICATION FOR DEFERRALS v 3 Justification for Applicability Status Deferral ~ CN-CA 01 CA to Steam Generator Checks Revised 06/29/96 CN-CA-02 Auxiliary Feedwater from Nuclear Service Water Checks Revised 06/29/96 , CN-CA-03 CA Pump Suction Checks Revised 06/29/96 CN-CA-04 CA Assured M/V from RC Checks Revised 06/29/96 CN-CA-05 CF to CA Nozzle Isolation Valves Revised 06/29/96 CN-CF-01 CF Isolations Revised 06/29/96 CN-FW 01 FWST to ND Pump Suction Checks Revised 06/29/96 CN-1A 01 Personnel Air Lock Isolation Checks Revised 06/29/96 CN-KC-01 KC to NCDT Hx. Isolation Valves Revised 06/29/96 CN KC-02 KC to NC Pump Containment Isolations Revised 06/29/96 CN-KC-03 KC Containment Check Revised 06/29/96 CN-KD-01 Diesel Generator KD Pump Discharge Check Revised 06/29/96 CN-NB-01 NB Containment Check Revised 06/29/96 CN-NC-01 NC Containment Check Revised 06/29/96 CN-NC-02 Reactor Coolant System PORV Revised 06/29/96 CN-NC-03 Reactor Vessel Head Vents Revised 06/29/96 CN-ND-01 NC to ND Pump A Isolations Revised 06/29/96 CN ND 02 NC to ND Pump B Isolations Revised 06/29/96
- CN-ND-03 ND Pump discharge Checks Revised 06/29/96
- CN-ND-04 ND Cross ConnectIsolations Revised 06/29/96
. CN-ND-05 ND Pump Supply to NV and NI Pumps Isolations Resised 06/29/96 1 CN-NF-01 NF Containment Isolation Check Resised 06/29/96
! CN-NI-01 NV to NC Injection Isolations Revised 06/29/96 CN-NI-02 NV to NC Injection Check Revised 06/29/96 L CN-NI-03 NI Pump to Cold Leg Checks Revised 06/29/96 CN-NI-04 NI Cold Leg Checks Resised 06/29/% CN-NI-05 NI to Accumulator N2 Supply Checks Resised 06/29/96 CN-NI-06 Cold Leg Discharge Checks Revised 06/29/96 CN-NI-07 FWST to NI Pumps Check Revised 06/29/96 CN NI-08 FWST to NI Pumps Isolation Revised 06/29/96 i CN-NI-09 NI Pump Recirculating Isolations Resised 06/29/96 CN-NI-10 NI Pump Discharge Checks Revised 06/29/96 CN NI l1 NI to Hot Legs Checks Revised 06/29/96 CN-NI-12 NI Cold Leg Isolation Revised 06/29/96 CN NI 13 NI to Cold Legs Checks Revised 06/29/96 CN NI 14 ND to Cold Legs Checks Revised 06/29/96 - CN NI 15 ND to Cold Legs Isolation Revised 06/29/96 CN-NI 16 NI to Hot LegsIsolation Resised 06/29/96 CN NI 17 Containment Sump Recirculating Isolations Resised 06/29/% CN-NI 18 ND Train A to NV Pump Suction Isolation Revised 06/29/96 CN NI-19 ND Train B to NI Pump Suction Isolation Revised 06/29/96 . CN-NI-20 ND Train B to NI Pump Suction Check Revised 06/29/96 CN NI 21 NI Pump Discharge to NC Loops Isolations Resised 06/29/% CN-NI-22 NIPumps MiniflowIsolations Revised 06/29/96 CN-NI-23 NI Pump Suction Isolations from ND and NV Revised 06/29/96 O Rev.23 ! Page 1 of 2 l
6.1 VALVE JUSTIFICATION FOR DEFERR.AL_S { V Justification for Applicability Status Deferral CN NS-01 FWST to NS Pump Checks Revised 06/29/% CN-NS-02 NS Spray Header Checks Resised 06/29/96 CN-NS 03 ND to NS Spray HeaderIsolations Revised 06/29/96 CN-NV-01 NV Letdown ContainmentIsolation Revised 06/29/96 CN-NV-02 NV to NC Pump Seals Return Header Cont. Isolation Revised 06/29/% CN-NV 03 NV to VCT OutletIsolation Revised 06/29/% CN-NV-04 NV Charging Line Containment Isolation Revised 06/29/96 CN-NV-05 NV Pump Suction to FWST Checks Revised 06/29/96 CN-NV 06 NV Pump to Charging Line Checks Revised 06/29/96 CN-NV 07 NV Pump MinillowIsolations Revised 06/29/% CN-NV-08 NV Pumps Section from ND Checks Revised 06/29/96 CN-NV-09 Standby M/U Pump Cont. Header Checks Revised 06/29/96 CN NV-10 NV Pumps Suction from FWST Revised 06/29/% CN-NV Il NV Letdown Orifice Outlet Valves Revised 06/29/96 CN-NV-12 NC to NV Letdown Isolation Revised 06/29/96 ' CN NW-01 NW Surge Chamber from RN Checks Revised 06/29/% CN-NW-02 NW Supply to Cont. Isolation Valses Check Revised 06/29/% CN-RF-01 RF to Containment Isolation Valve Checks Revised 06/29/% CN RN-01 RN-Upper Containment Vent Unit Checks Revised 06/29/96 g CN-RN-02 RN to Lower Containment Vent. Units Supply Header Cont. Isol. Revised 06/29/96 CN RN-03 RN to Lower Containment Vent. Units Return Header Cont. Isol. Resised 06/29/96 CN-SA-01 Main Steam to CAirr Checks Revised 06/29/96 CN SM-01 Main Steam Containment isolations Revised 06/29/96 CN-VB-01 VB Containment Isolation Valves Revised 06/29/96 CN-VG-01 D/G Starting Air Checks Revised 06/29/96 CN VG-02 D/G Starting Air Checks Revised 06/29/96 CN-VI-01 VI Containment Header Checks Revised 06/29/96 CN-VI-02 VI Containment Isolation Valves Resised 06/29/96 CN-VI 03 N2 to NC PORV Checks Revised 06/29/96 CN-VI-04 N2 to NC PORY Checks Revised 06/29/96 CN-VS 01 VS to Unit 1 Containment Header Checks Revised 06/29/96 CN-VY-01 VY Containment Isolation Valve Checks Revised 06/29/96 CN-YM-01 YM Containment Isolation Checks Revised 06/29/96 1 A* t
'd Rev.23 Page 2 of 2
Catar/ba Units 1 and 2 - O V - Justification for Deferral item Number: CN-CA-01 Valve: ICA037, ICA041, ICA045, ICA049, ICA053, ICA057, ICA061, ICA065 2CA037, 2CA041, 2CA045, 2CA049, 2CA053, 2CA057, 2CA061, 2CA065 Flow Diagram: CN 1592-1.1 CN-2592 1.1 Code Category: C e ASME Class: 2 {
- Function: Open to allow Auxiliary Feedwater (CA) System supply to the steam
- generators.
Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its
- s function every three months per Oma-1988 Part 10,4.3.2.1. l 4
4 Basis for Deferral: Full stroke testing these valves during power operation would unnecessarily thermal shock the steam generators and feedwater PIiP ng. Test Alternative & Frequency: Valves will be full stroke exercised following each cold shutdown of ; greater than 30 days prior to entering Mode 2. I l l l l l I l i l l I l O 06/29/96 CN-CA 01 Rev.23 Page1of I Section 6.1 l 1
l-Cctawba U::its I cnd 2 P O Justification for Deferral item Number: CN-CA 02 Valve: ICA171, ICA172 2CA171,2CA172 ) Flow Diagram:' CN-1592 1.0 i- CN-2592 1.0 Code Categosy: C ASME Class: 3 J Function: Open to allow assured makeup to Auxiliary Feedwater (CA) System from the Nuclear Service Water (RN) System on RN to CA swapover signal. i f% Close to prevent diversion of flow when the system is in operation and V RN to CA swapover has occurred it its associated RN train is out of serv 1cC. q_ Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its 4 function every three months per Oma-1988 Part 10,4.3.2.1. Check valve reverse flow test per GL 89-04. i j' Basis for Deferral: Full stroke testing these valves would unnececerily contaminate the CA system with RN water. No means exist to test for valve closure. a
- Test Alternative & Frequency
- Exercise check valve (partial stroke) to the position required to fulfill
- its function every three months. During each refueling outage, one of the two check valves will be disassembled and the disk will be mechariically exercised. During the next refueling outage, the other valve will be disassembled, such that each valve will be tested in a two refueling outage time period. Should one valve fail to stroke
., acceptably, the other valve will also be disassembled. During each refueling outage, one of the two check valves will be disassembled and checked for proper seating capability. During the next refueling outage, the other valve will be disassembled, such that each valve will be tested in a two refueling outage time period. Should one valve indicate improper seating capability, the other valve will also be disassembled.
"p i
06/29/96 CN-CA-02 -
'Rev.23 Page1of 1 Section 6.1
Cct:wba Units 1 and 2 i Justification for Deferral i Item Number: CN-CA 03 Valve: ICA008, ICA010, ICA012 2CA008,2CA010,2CA012 Flow Diagram: CN-1592 1.0 CN-2592 1.0 Code Category: C ASME Class: 3 Function: Close to prevent diversion of flow when the system is in operation and a Nuclear Service Water. (RN) to CA swapover or Condenser Circulating Water (RC) to CA swapover has occurred. l
/ Test Requirement: Check valve reverse flow test per GL 89-04. ; \
Basis for Deferral: Past leak rate testing during refueling outages has indicated no reverse flow problems. Based upon the past results, and limits on scope of testing due to piping configuration, the reverse flow test requirements j will now be satisfied by sample disassembly. i Test Alternative & Frequency: During each refueling outage, one of the three check valves will be disassembled checked for proper seating capability. During the j subsequent refueling outage, the other valves will be disassembled
)
(one per outage),such that each valve will be tested in a three refueling : outage time period. Should one valve indicate improper seating capability, the other two valves will also be disassembled. l O 06/29/96 CN-CA-03 Rev.23 Page1of I Section 6.1 _ _ _ _ _ _ _ _ _ _ - _l
Catawba Units 1 c::d 2 - O v Justification for Deferral Item Number: CN-CA-04 Valve: ICA173 - 2CA173 Flow Diagram: CN-1592-1.0 CN 25921.0 Code Category; C ASME Class: 3 . Function: Open to allow assured makeup to Auxiliary Feedwater (CA) System ; from the Condenser Circulating Water (RC) System on RC to CA swapover signal, and allow RC supply to the Turbine Driven CA Pump in the event requiring use of the Standby Shutdown Facility O (SSF). Close to prevent diversion of flow when the system is in operation and Nuclear Service Water (RN) to CA rwapover and RC to CA swapover has occurred. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every three months per Oma 1988 Part 10,4.3.2.1. Check valve reverse flow test per GL 89-04. i Basis for Deferral: Stroke Testing this valve would unnecessarily contaminate the CA system with RC water. No means exist to test for valve closure. h Test Alternative & Frequency: During each refueling outage, the check valves will be disassembled and the disk will be mechanically exercised. During each refueling outage, the check valve will be disassembled and checked for proper seating capability. f 06/29/96 CN-CA 04 Rev.23 Page1of 1 Section 6.1
. - - . ._. .- - . - ,.- - - =, - - _ . -
Cct wb2 Unit 2
- O d
i : 3 Justification for Deferral 4 4 Item Number: CN-CA 05 Valve: 2CA149,2CA150,2CA151, ICA152 a Flow Diagram: - CN-2592-1.1 Code Category: B ASME Class: 2
- Function
- Close on Feedwater Isolation signal and Phase "A" Containment
' Isolation signal. 4- Test Requirement: Exercise valve (full stroke) to the position required to fulfill its j- function every three months per OMa-1988 Part 10, 4.2.1.2. Test valve for fait safe actuation every three months per OMa-1988 Part 10, 4.2.1.6. Stroke time valve (full stroke) every three months per OMa-
\ 1988 Part 10,4.2.1.8.
. Basis for Deferral: The Westinghouse D 5 steam generator design requires these valves to
- f. be used for a portion of the main Feedwater flow during power
- operation. Closing these valves at 100% power would isolate this flow, possibly resulting in preheater damage.
Test Alternative & Frequency: These valves willbe: exercised (full stroke) during cold shutdown, tested for fail safe actuation during cold shutdown, 3 and stroke timed tested during cold shutdown. a 1 e 4 06/29/96 CN-CA-05 Rev.23 Page1of 1 i Section 6.1
Catawba Units 1 and 2 (OU) dHgification for Deferral Item Number: CN-CF-01 Valve: 1CF033,1CF042,1CF051,1CF060 2CFv33,2CF042,2CF051,2CF060 Flow Diagram: CN-1591 1.1 - CN 2591-1.1 Code Category: B ASME Class: 2 Functb- Isolates main feedwater piping from the steam generators upon receipt of a feedwaterisolation signal. V Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function, observe fail-safe operation, and stroke time every 3 months. Basis for Deferral: Closing these valves during power operation is considered impractical from an operating viewpoint. Closure would isolate feedwater to the steam generator which may result in a severe transient in the steam generator, possibly causing a unit trip. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function, fail-safe operation verified, and stroke timed during cold shutdown. O O 06/29/96 CN-CF-01 Rev. 23 Page 1 of 1 Section 6.1 a l
C:t:wb2 Units 1 c d 2 i:lO Justification for Deferral item Number: CN-FW 01 Valve: IFWO28, IFWOS6 2FWO28,2FW0%
- Flow Diagram: CN-1571-1.0 CN-2571 1.0 Code Category: C-ASME Class: -2 Function: Opens on flow from Refueling Water Storage Tank to suction of : ,
Residual Heat Removal Pumps. Test Requirement: Exercise check valve (Full Stroke) to the position required to fulfill its function every 3 months. Basis for Deferral: These valves can only be full stroke tested with the residual heat removal pump operating at full flow in recirculation to the refueling water storage tank. To do this requires closing one of the cold leg injection cross-tie valves and opening the manual valve (IND033) (2ND033) leading back to the FWST. Based on Design Engineering and Westinghouse evaluation, this renders both trains of ND , inoperable. This is not allowed by Technical Specification 3/4.5.2 in Modes.1-3 since both trains are required to'be operable. Technical Specification 3/4.5.3 requires one train of ND to be operable in Mode 4. ! Test Alternative & Frequency: Full Str'oke testing will be performed during cold shutdown. Valves i will be partial stroked quarterly. t i 06/29/96 CN-FW-01 Rev.23 Page1of 1 ' Section 6.1 1 m - m a, . - + w - , - - " - >~
C:tawb2 U::its I c:d 2 p ' Justification for Deferral 4 J ltem Number: CN-IA-01 Valve: IIACV5340, llACV5350, IIACV5360, IIACV5370, IIACV5380, IIACV5390 21ACV5340, 21ACV5350, 21ACV5360, 21ACV5370, 21ACV5380, 21ACV5390 ' Flow Diagram: CN-1499 IAl.01 CN-2499-IA1.01 Code Category: A, C , , ASME Class: 2 Function: Provides containment isolation. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its
- function every 3 months. l Basis for Deferral: System design does not provide any indication for verifying valve i a
closure upon flow reversal. Test Alternative & Frequency: Verify valve closure during performance of leak rate test during refueling. { l l i i
)
J l O CN-IA-01 l 06/29/96 Rev.23 Page1 of 1 Section 6.1
Catawha Units I c:d 2
.i D V t Justification for Deferral 1-Item Number: CN-KC 01 Valve: IKC320A, IKC332B,1KC333A 2KC320A,2KC332B,2KC333A Flow Diagram: CN-1573-1.3 i CN-2573 1.3 Code Category: B l
j ASME Class: 2 Function: Isolates flow to the reactor coolant drain tank heat exchanger upon l receipt of a high containment pressure signal. r Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function and stroke time every 3 months. Basis for Deferral: Failure of one of these valves in the closed position during testing would inhibit the flow path through the reactor coolant drain tank heat exchanger. This would result in boiling of the water in the reactor ) coolant drain tank resulting in excess heat in containment. This j increased heat load could cause unit shutdown due to exceeding Tech ] Spec containment temperature limits. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. I f i l
\
P 06/29/96 CN-KC-01 i
- Rev 23 - Page1 of I l Section 6.1
-_-__---___-____J
Cct wbs Units I crd 2 - ,
. O .
i s Justification for Deferral i i Item Number: CN-KC 02
- t Valve: 1KC338B,1KC424 B,1KC425A
; 2KC338B,2KC424 B,2KC425A Flow Diagram: CN-1573 1.3 CN-2573-1.3 Code Category: B .
i ~ ASME Class: 2 < c Function: 1solates flow to the reactor vessel support coolers, reactor coolant ' pump motor bearing coolers, and reactor coolant pump thermal 3 barriers, upon reaipt of a high-high containment pressure signal. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function and stroke time every 3 months. Basis for Deferral: Failure of these valves in the closed position during testing would inhibit flow to the reactor vessel support coolers, reactor coolant pump i motor bearing coolers, and reactor coolant pump thermal barriers. ; This action could result in unit shutdown and possible damage to the i vessel and reactor coolant pumps. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. t. I, i e i i O ! 06/29/96 CN KC 02 Rev. 23 Page1of 1 Section 6.1 l c .-n . ,..
Cetr/bs Units 1 cnd 2 gf3
- U h
I i Justification for Deferral I Item Number: CN-KC-03 i !' Valve: IKC280, IKC340
' 2KC280,2KC340 .
t . Flow Diagram: CN 15731.3 ! CN-2573 1.3 e j Code Category: A/C ; ASME Class: 2 l { . Function: Provides containment isolation. l - Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its . safety function every 3 months. Basis for Deferral: System design does not provide any indication for verifying valve closure upon flow reversal. i Test Alternative & Frequency: Verify valve closure during performance of leak rate test during i refueling. i h d 1 i 4 B e 1 ,. y 06/29/96 CN-KC-03 Rev.23 Page1of 1
. Section 6.1 1
j Cctwb2 Udits I cnd 2 3
- l' 4 >
1 i Justification for Deferral 1 Item Number: CN-KD-01 ]
, Valve: IKD006,1KD021 i 2KD006,2KD021 i
! Flow Diagram- CN 1609-1.0 - - CN 26091.0 i. Code Category: C ASME Class: 3 f i Function: Opens on diesel engine start to pass cooling water flow from the diesel generator engine drivenjacket water circulation pump. l Test Requirement: Exercise valve (full stroke) to the position required to fulfill its
- _ O function every 3 months.
.V-Basis for Deferral: Valve design does not provide any indication of position. Test Alternative & Frequency: Valves will be verified to operate during monthly Tech Specs Diesel Test (IT/1/A/4350/02A. B - Diesel Generator A, B Operability Test) , (IT/2/A/4350/02A, B - Diesel Generator A, B Operability Test) by verifying proper cooling is supplied during diesel run. In addition, the valves will be disassembled (as required by IE Bulletin i No. 83-03) during each refueling and the mechanical integrity of the valve internals verified. I O ~ 06/29/96 CN-KD-01 Rev,23 Page1of I Section 6.1
i Catawba Units 1 and 2 i i ! Justification for Deferral Item Number: CN-NB-01 t i l i Valve: INB262 ; 2NB262 I Flow Diagram: CN 1556-2.0 j CN-1556 2.0 4 Code Category: A,C ASME Class: 2 4 e Function: Provides containment isolation. 1 1 Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every three (3) months. 1 i l Basis for Deferral: System design does not provide any indication for verifying valve closure upon flow reversal. Test Alternative & Frequency: Verify valve closure during performance ofleak rate test during refueling. j O 06/29/96 CN-NB-01 Rev.23 Page1ofI Section 6.1
Cctawba U::its I c::d 2 O , Justification for Deferral item Number: CN-NC 01 Valve: INC057 2NC057 Flow Diagram: CN-1553-1.1 CN-2553-1.1 Code Category: A/C ASME Class: 2 i Function: Provides containment isolation. l Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its l ( function every 3 months. l Basis for Deferral: System design does not provide any indication for verifying valve closure upon flow reversal. Test Alternative & Frequency: Verify valve closure during performance cf leak rate test during refueling. I l i 06/29/96 CN NC-01 Rev.23 Page1of I Section 6.1
C tawba Units I c:d 2 Justification for Deferral Item Number: CN-NC 02 Valve: INC032B, INC034A, INC036B - 2NC032B,2NC034A,2NC036B Flow Diagram CN-15531.1 CN 25531.1 Code Category: B ASME Class: 1 Function: Reactor Coolant System PORV opens to relieve pressure for the Primary system. l Test Requirement: Stroke time and observe fail-safe operation every three (3) months. Basis for Deferral: PORVS do not serve a safety function when unit is at operating temperature and pressure. PORVs protect the Reactor Coolant System from over pressurization during LTOP conditions 1(2)NC032B & 1(2)NC034A only. Also according to NRC Branch Tecimical Position RSB5 2 the full stroke exercise should take place during cold shutdown vs. quarterly during power operations due to the high probability of sticking open. Tech Spec 4.4.4.1 prevents Catawba from performing the surveillance test in Modes 1 and 2. Test Ahernative & Frequency: Stroke time testing and fail-safe observation will be performed at cold shutdown for 1(2)NC032B,1(2)NC034A, & 1(2)NC036B; and in all cases prior to entering LTOP conditions in accordance with Generic Letter 90-06 for 1(2)NC032B & 1(2)NC034A. Testing will not be required more often than once per qaarter as defined in Oma-1988 Part 10,4.2.1.1. !' I O 06/29/96 CN NC 02 Rev.23: Page1of 1 Section 6.1
. . .. . . . .- - ~ . . - . . - . . . . . . -.- . . - . . . - . -
Cctawba Units 1 c::d 2 K ( Justification for Deferral item Number: CN-NC-03 Valve: INC250A, INC251B, INC252B, INC253A 2NC250A,2NC251B,2NC252B,2NC253A Flow Diagram CN 15531.1 - . CN-2553 1.1 Code Category: B ASME Class: 1 Function: Reactor vessel head vent. Test Requirement: Stroke time test in ace rdance with Oma-1988 Part 10,4.2.1.1. Basis for Deferral: Opening these valves at full pressure could cause damage to the valve seating surfaces A reactor coolant leak could be caused, j Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown. ! 06/29/96- CN-NC-03 Rev.23 Page1of I Section 6.1
Catriba Urlts I cnd 2' s
- (3
.v 1
Justification for Deferral ' Item Number: CN-ND-01
+
s Valve: IND001B, IND002A 2ND001B,2ND002A Flow Diagram: CN-1561 1.0 CN-2561-1.0 Code Category: A ASME Class: 1 1 Function: Valves open to provide suction to Residual Heat Removal Pump A during normal unit cooldown. I Ten Requirement: Exercise valve (full stroke) to the position required to fulfill its function and stroke time every 3 months. Basis for Deferral: These valves have been provided with an interlock which prevents their opening when Reactor Coolant System pressure is above approximately 425 PSIG. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. l l, l 1 I 06/29/96 CN-ND-01 Rev.23 Page1of I Sec* ion 6.1 u
Cst:wba Units 1 and 2 _;
- 0
%,/
Justification for Deferral Item Number: CN-ND 02 Valve: IND036B, IND037A 2ND036B,2ND037A
. Flow Diagram: CN-1561-1.1 CN 2561-1.1 Code Category: A l
. ASME C ass: 1 l
Function: Valves open to provide suction to Residual Heat Removal Pump B during normal unit cooldown. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function and stroke time every 3 months. Basis for Deferral: These valves have been provided with an interlock which prevents their opening when Reactor Coolant System pressure is above approximately 425 PSIG. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. i i i :1 d 4 1 p I I 06/29/96 CN-ND 02
- Rev.23 Page1of 1 2
Section 6.1
Cctswbn U:its I cnd 2 (3 L) Justification for Deferral item Number: CN-ND-03 Valve: IND010, IND044 2ND010,2ND044 Flow Diagram CN 1561 1.0, CN-1561 1.1 , CN-2561 1.0, CN-2561 1.1 l a Code Category: C ASME Class: 2 Function: Residual heat removal pump discharge check valve. Test Requirement: Exercise check valve (Full Stroke) to the position required to fulfill its function every 3 months. 1 Basis for Deferral: These valves can only be full stoke tested with the residual heat removal pump operating at full flow in recirculation to the refueling water storage tank. To do this requires closing one of the cold leg injection cross-tie valves and opening the manual valve (IND033) (2ND033) leading back to the FWST. Based on Design Engineering and Westinghouse evaluation this renders both trains of ND inoperable. This is not allowed by Technical Specification 3/4.5.2 in Modes 1-3 since both trains are required to be operable. Technical Specification 3/4.5.3 requires one train of ND to be operable in Mode 4. Test Alternative & Frequency: These valves will be exercised (Partial Stroke) by operating the residual heat removal pump in minimum flow mode every 3 months. These valves will be exercised (Full Stroke) during cold shutdown. O 06/29/96 CN-ND-03 Rev.23 Page1of 1 Section 6.1
' i Cstawba Units 1 cnd 2 . < l L Justification for Deferral
- .l Item Number
- CN-ND-04 1 l
l Valve: IND032A, IND065B 2ND032A,2ND065B l Flow Diagram: CN-1561 1.0, CN-1561 1.1 I s CN-2561-1.0, CN-2561-1.1 '
- Code Category
- B i
ASME Class: 2 { Function: Cross connect cold leg injection flow path from the two trains of I ! residual heat removal I Test Requirement: Exercise valve (Full Stroke) to the position required to fulfill its function and stroke time every 3 months. { Basis for Deferral: Based on Design Engineering and Westinghouse evaluation, closing , one of these valves renders both trains of residual heat removal l inoperable. This is not allowed by Technical Specification 3/4.5.2 in Modes 1-3 since both trains are required to be operable. Technical Specification 3/4.5.3 requires one of train of ND to be operable in Mode 4. Test Alternative & Frequency: Valves will be exercised (Full Stroke) to the position required to fulfill its function and stroke timed during cold shutdown. j 06/29/96 CN-ND-04 Rev.23 Page1of 1 1 1 Section 6.1
Cct:wba Units 1 cad 2
'd i
Justification for Deferral Item Number: CN-ND-05 Valve: IND028A . 2ND028A i' Flow Diagram: CN-1561 1.0 CN-2561 1.0 Code Category: B ASME Class: 2 Function: Residual Heat Removal pump supply to NV and NI pumps. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its , function and stroke time every 3 months. Basis for Deferral: Opening valve provides flow path from FWST to suction of centrifugal l charging pumps. This could result in a plant transient due to an I l increase in RCS Boroninventory, I Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. , I v 06/29/96 CN-ND-05 Rev.23 Page1 of I Section 6.1.
i Catawba Units I and 2.
/
T% Justification for Deferral l Item Number: CN-NF 01 Valve: INF229 2NF229 Flow Diagram: CN-1558-2.0 CN-2558-2.0 Code Category: A, C
' ASME Class: 2 Function:
Provides contammentisolation. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 montla. Basis for Deferral: System design does not provide any indication for verifying valve closure upon flow reversal. Test Alternative & Frequency: Verify valve refueling. closure during performance of leak rate test durin i 2 , L) 06/29/96 Rev.23 CN-NF-01 Page1of I Section 6.1
l Cctawba Units 1 cud 2 0
- i
'd ~\
l l l Justification for Deferral ) Item Number: CN-NI-01 Valve: INI009A, INIO10B 2N1009A,2N1010B Flow Diagram: CN 15621.0 CN-2562-1.0 Code Category: B ASME Class: 2 p) ( Function: Opens to allow flow from centrifugal charging pump discharge to reactor coolant loop cold leg. Test Requirement: Exercise valve (Full Stroke) to the position required to fulfill its function and stroke time every 3 months. 4 Basis for Deferral: Exercising these valves quarterly during power operations would result in flow of non-preheated water through the injection lines and thermal shocking of the injection nozzles. , Test Alternative & Frequency: Valve will be exercised (Full Stroke) to the position required to fulfill its function and stroke timed during cold shutdown. . 1 t , s 4 4
. (.
06/29/96 CN NI-01. Rev.23 Page1of 1 , Section 6.1
A Catnwba Ucite 1 cad 2
./ '
d i Justification for Deferral item Number: CN-NI-02 i - ! Valve: IN1012
. 2N1012 i Flow Diagram: CN-1562 1.0 CN-2562 1.0 l Code Category: C ASME Class: 2
, Function: Opens on flow from the Centrifugal Charging Pumps. , Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its b O function every 3 months. j Basis for Deferral: Using a centrifugal charging pump to provide flow to (INIO12) . (2N1012) would result in injecting borated water into the Reactor l Coolant System through the cold leg injection lines. This would result 1 in thermal shock to the reactor coolant piping. During cold shutdowns exercising this valve could result in a low temperature ! overpressurization of the reactor coolant system. Test Alternative & Frequency: Exercise check valve (full stroke) to the position required to fulfill its i < function at refueling.
- i l l 06/29/96 CN-NT-02 Rev.23 Page1of I Section 6.1
2 Cctswba' Units 1 cnd 2
', : /m
- U l
I
; Justification for Deferral 4
' Item Number: CN-NI-03 4
Valve: IN1015, IN1017, INI019, IN1021, INI351, IN1352, INI353, INI354 5 2NIO15, 2N1017, 2NIO l9, 2NIO21, 2NI351, 2N1352, 2NI353, 2NI354 Flow Diagram: CN-1562-1.0 CN-2562-1.0 Code Category: C ASME Class: 1 :
)
f Function: These valves open on flow from the Centrifugal Charging Pumps. l ! Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its l p function every 3 months. , i Basis for Deferral: Operating these valves would require using a centrifugal charging l pump to provide flow which would result in injecting borated water ] into the Reactor Coolant System thereby causing thermal shock to the 1 reactor coolant piping. During cold shutdowns exercising this valve i could result in a low temperature overpressurization of the reactor ) i coolant system. l Test Alternative & Frequency: Exercise check valve (full stroke, to the position required to fulfill its 1 - function at refueling. I
. l
- i I l 1 ;
c :
)
r l i O ! G l
'06/29/96 CN-N1-03 Rev.23 Page1of 1 Section 6.1
Cetrwb2 Units I c d 2 Justification for Deferral item Number: CN NI-04 Valve: IN1060, INIO71, INIO82, IN1094 2NIO60,2N1071,2N1082,2NIO94 Flow Diagram: CN 1562-1.1 CN-2562 1.1 Code Category: A, C ASME Class: 1 Function: Opens on flow from the cold leg accumulators, safety injection pumps or residual heat removal pumps to provide flow to the reactor coolant system cold legs. O V Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. Basis for Deferral: These valves cannot be full or part stroke exercised during power operation since safety injection pump discharge pressure (approximately 1520 psig) cannot overcome reactor coolant system pressure. Test Alternative & Frequency: Exercise check valve (partial stroke) to the position required to fulfill 1 its function at cold shutdown. During each refueling, one of the four check valves will be disassembled and the disk will be mechanically exercised. The next refueling, a different valve in this group will be disassembled, and so on, such that all four valves will be tested within a four refueling time period. Should any one valve fail to stroke acceptably, the remaining three valves will also be disassembled. O U ! 06/29/96 CN NI 04 Rev.23 Page1of 1 Section 6.1 I l
. . _- _ . . _ . . _ _ . . . . _ _ _ ~ _ _ . _ . _ . _ . _ _
4 . Ccts /ba Ucits 1 cnd 2 ~
's L. (V 4
Justification for Deferral Item Number: CN-N105 Valve: 1N1048,2NIO48 Flow Diagram: CN-1562 1.1 CN-2562 1.1 l Code Category: . A, C ] ASME Class: 2 Function: Provides containment isolation. i Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months.
' C Basis for Deferral: System design does not provide any indication for verifying valve .( closure upon flow reversal.
- . Test Alternative & Frequency; Verify valve closure during performance of leak rate test during refueling.
i A 4 O) N, 06/29/96 CN-N1-05 Rev.23 Page1 of 1 Section 6.1 2 i
Cctawbn U::lts 1 c::d 2 (R Rf Justification for Deferral item Number: CN-NT46 Valve: IN1059, IN1070, IN1081, IN1093 2N1059,2N1070,2N1081,2N1093 Flow Diagram: CN-15621.1 CN-2562-1.1 Code Category: . A, C ASME Class: 1 Function: Opens on flow from the cold leg accumulators to provide flow to the reactor coolant system cold legs. n Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its I function every 3 months. Basis for Defenal: These valves cannot be full or part stroke exercised during power operations since cold leg accumulator pressure (approximately 600 psig) cannot overcome reactor coolant system pressure. During cold shutdown exercising these valves could result in a low temperature overpressurization of the reactor coolant system. Test Alternative & Frequency: During approach to or startup from cold shutdown, these valves will be partial stroked by opening associated Cold Leg Accumul- : solation valve and noting decrease in level. During each refuel; .g, one of the four check valves will be disassembled and the disk will be mechanically exercised. The next refueling a different valve in this group will be disassembled, and so on, such that all four valves will be tested within a four refueling time period. Should any one valve fail to stroke acceptably, the remaining three valves will also be disassembled. m i 06/29/96 CN-N1-06 Rev.23- Page1of 1 Section 6.1
Cctenb2 Units 1 and 2 10
.(_)
Justification for Deferral item Number: CN-NI-07 Valve: IN1101 2N1101 Flow Diagram: CN-1562-1.2 CN-2562 1.2 Code Category: C ASME Class: 2 Function: Opens to provide flow from refueling water storage tank to safety injection pumps suction. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. Basis for Deferral: Valves cannot be full stroke exercised during power operation since U the only full flow flowpath discharges into the reactor coolant system. Safety injection pump discharge pressure (~1520 psig) cannot overcome reactor coolant system pressure During cold shutdown this valve cannot be full stroke exercised since this could result in a low temperature overpressurization of the reactor coolant system. Test Alternative & Frequency: Exercise check valve (partial stroke) to the position required to fulfill its function every 3 months and exercise check valve (full stroke) to the position required to fulfill its function during refueling. i f d 06/29/96 CN-N1-07 Rev.23 Page1 of I Section 6.1 4
Cct:wbs Units 1 cnd 2 Justification for Deferral l i Item Number: CN-NI 08
. Valve: IN!!00B .
2 nil 00B l Flow Diagram CN 1562-1.2 CN-2562-1.2 Code Category: B ASME Class: 2 Function: Provides suction for both trains of safety injection pumps from the refueling water storage tank. ? Test Requirement: Exercise valve (full stroke) to the position required to fulfill its 4 O V function and stroke time every 3 months. Basis for Deferral: Failure of this valve in the closed position during testing would render both trains of safety injection pumps inoperable. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdow11. 1 I i i 1 .. i; i. L
\s 06/29/96 CN-NI 08
" Rev. 23 Page1of 1 Section 6.1 4
. = . . .. . .. .
L Cctawba Units 1 and 2 ?
,O V
Justification for Deferral item Number: CN-NI-09 Valve: INil47B 2 Nil 47B Flow Diagram: CN-1562-1.2 CN-2562 1.2 Code Category: B ASME Class: 2 Function: Valve is normally open to provide miniflow path to the refueling water storage tank.
.p Test Requimment: Exercise valve (full stroke) to the position required to fulfill its function and stroke time every 3 months.
Basis for Deferral: Failure of this valve in the closed position during testing would result in loss of miniflow path for both trains of safety injection pumps. This would result in pump damage due to dead heading the safety injection pumps in the event of a safety injection signal with reactor coolant pressure above 1520 psig (Safety Injection Pump Discharge Pressure). Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. 06/29/96 CN-NI-09 Rev.23 Page1of 1 Section 6.1
_ _ . _ ~ . _ . . . ~ . . _ . . _ _ _ _ _ - . . _ . . .. 5 Cet:wba Uzits 1 a:d 2
-f% , U ,
i 1 Justification for Deferral i Item Number: CN-NI 10 l ; Valve: INill6, INll48 { 2 Nill 6,2 Nil 48 3 l . Flow Diagram:. CN 15621.2 l- CN-2562 1.2 [- Code Category: C ASME Class: 2 Function: Opens on flow from the safety injection pumps to the reactor coolant coldlegs or hot legs. \ Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months.
- Basis for Deferral
- Valves cannot be full or partial stroke exercised during power
< operation since the only flowpath discharges into the reactor coolant system. Safety injection pump discharge pressure (~1520 psig) cannot
- overcome reactor coolant system pressure. During cold shutdown l these valves cannot be full or partial stroke exercised since this could j result in a low temperature overpressurization of the reactor coolant system.
Test Alternative & Frequency: Exercise check valve (full stroke) to the position required to fulfill its ! function at refueling. i k i i . i- !! 4 i 06/29/96 CN NI-10 Rev.23 Page1of I l Section 6.1
.. . - . . - - . . ~ . . . - . . - . .. - - . . . . . - 9 Cct:.wb3 Urits 'l cnd 2' O - Justification for Deferral Item Number: CN-NI l1 Valve: INIl24, INIl26,1 nil 28, INIl34, INI156, INIl57, INIl59, INIl60 2NI124, 2NI126, 2NI128, 2NI134, 2NI156, 2 Nil 57, 2NI159, 2NI160
' Flow Diagram: CN-1562 1.2 CN-2562-1.2 Code Category: A, C ASME Class: 1 Function: These valves open to provide hot leg recirculation flow from the safety injection pumps.
g Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. (
. Basis for Deferral: Valves cannot be full or partial stroke exercised during pour operation since the only flowpath discharges into the reactor coolant system. Safety injection pump discharge pressure (~1520 psig) cannot overcome reactor coolant system pressure During cold shutdown i these valves cannot be full or partial stroke exercised since this could )
result in a low temperature overpressurization or the reactor coolant j j system. Test Alternative & Frequency: Exercise check valve (full stroke) to the position required to fulfill its function at refueling. l l 1 i ( D) l 06/29/96 CN-NI-11 Rev.23 Page1of 1 i Section 6.1 1
i C t:wba Units 1 and 2 O Justification for Deferral i Item Number: CN-NI 12 l Valve: INil62A 2 nil 62A Flow Diagram: CN-1562 1,3 ! CN-2562-1.3 Code Category: B l ASME Class: 2 l Function: Valve is normally open to provide cold leg injection flow from both trains of safety injection pumps. l Tr tPequirement: Exercise valve (full stroke) to the position required to fulfill its O function and stroke time every 3 months. Basis for Deferral: Failure of this valve in the closed position during testing would result in loss of cold leg injection flow from the safety injection pumps j rendering both trains of safety injection inoperable. ; l Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. i l l l l i i
)
i i i 06/29/ % CN NI-12 l 1Rev.23 Page1 of I ! Section 6.1
- . - . . . ~. . _
Cctawba Units 1 c:d 2 Justification for Deferral Item Number: CN-NI-13 Valve: IN1165, INIl67, INIl69, INIl71 ' 2 nil 65,2N1167,2 Nil 69,2 nil 71 Flow Diagram: CN-1562-1.3 CN 2562-1.3 Code Category: A, C ASME Class: 1 Function: Valves open on cold leg injection flow from the safety injection j pumps. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its 4 function every 3 months. Basis for Deferral: Valves cannot be full or partial stroke exercised during power operation since the only flowpath discharges into the reactor coolant system. Safety Injection Pump Discharge Pressure (~ 1520 psig) cannot overcome reactor coolant system pressure. During cold shutdown these valves cannot be full or partial stroke exercised since this could result in a low temperature overpressurization of the reactor coolant system. J Test Alternative & Frequency: Exercise check valve (full stroke) to the position required to fulfill its , function at refueling. l I l l l l l
% l 06/29/96 CN-NI-13 Rev.23 Page1of I Section 6.1
Cctswba Units 1 cnd 2 i Justification for Deferral 1 Item Number: CN-NI-14 ,- Valve: INIl75, INil76, INIl80, INIl81 2NI175,2NI176,2 nil 80,2 nil 81
) Flow Diagram: CN-1562-1.3 CN 25621.3 l
- Code Category
- A, C ASME Class: 1 I Function: Valves open on cold leg injection from the residual heat removal Pumps.
- 1. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its ;
- j. function every 3 months.
Basis for Deferral: Valves cannot be full or partial stroke exercised during power i operations since the only flowpath discharges into the reactor coolant system. Residual Heat Removal Pump discharge pressure (~210 psig) cannot overcome reactor coolant system pressure. Test Alternative & Frequency: Valves will be partial stroke exercised during cold shutdown. The valves will be full stroke exercised at refueling by sample disassembly or other NRC accepted means. i 4 4
\
l 06/29/96- CN-NI-l4 Rev.23' Page1of 1 Section 6.1
4 Cctanba Ucits 1 and 2 13 V Justification for Deferral item Number: CN-NI 15 i Valve: INI173A,1NI178B 2N!!73A,2 nil 78B Flow Diagram CN-1562-1.3 - CN 25621.3 I Code Category: B ASME Class: 2 - Function: Each valve isolates two of the four cold leg injection flow paths from 4 the residual heat removal discharge crossover line. Test Requirement: Exercise (Full Stroke) to the position required to fulfill its function and p (j stroke time every 3 months. Basis for Deferral: Based on Design Engineering and Westinghouse evaluation, closing one of these valves renders both trains of residual heat removal inoperable. This is not allowed by Technical Specification 3/4.5.2 in Modes 1-3 since both trains are required to be operable. Technical Specification 3/4.5.3 requires one train of ND to be operable in Mode 4. f Test Alternative & Frequency: Valves will be exercised (Full Stroke) to the position required to fulfill its function and stroke timed during cold shutdown. l
- i O
06/29/96 CN-NI-15 Rev.23 Page1of 1 J Section 6.1
Cat wb2 Urits 1 a d 2 n.
' id. .'
Justification for Deferral Item Number: CN-NI-16 Valve: INIl83B 2 Nil 83B Flow Diagram: CN 1562-1.2 CN-2562-1.2 Code Category: B l ASME Class: 2 I Function: - Opens to align hot leg injection during recirculation phase following safetyinjection actuation.
- Test Requirement: Exercise valve (Full Stroke) to the position required to fulfill its function and stroke time every 3 months.
I Basis for Deferral: Based on Design Engineering and Westinghouse evaluation, in order for a train of ND to be operable to perform its ECCS function, it must be able to discharge into all four cold leg injection lines. This is in the event of single train failure. With this additional valve open, one ND , pump could then be aligned to all four cold leg injection paths plus two hot leg paths during an ECCS actuation. Test Alternative & Frequency: Valve will be exercised (Full Stroke) to the position required to fulfill its function and stroke timed during cold shutdown. i-s 4 6 06/29/96 CN NI 16 Rev.23 Page1of 1 Section 6.1
l I C tawbs Uzits 1 cad 2 1 l l 1 1 Justification for Deferral : Item Number: CN-NI 17 , I Valve: INIl84B,'1NI185A 2 nil 84B,2NI185A Flow Diagram: CN 1562-1.3 CN 2562-1.3 Code Category: B l I ASME Class: 2 1 l Function: Opens to provide flow from the Containment Sump to the suction of Residual Heat Removal and Containment Spray Pumps during post i accident recirculation phase. Test Requirement: Exercise valve (Full Stroke) to the position required to fulfill its O function and stroke time every 3 months. Basis for Deferral: To prevent water from entering lower containment when cycling these ! valves, piping downstream must be drained. This results in making l one train of ECCS inoperable for an extended period of time until ; completion of the test, refilling the piping and realignment ofisolation j valves. Also, the large amount of potentially contaminated water that must be drained is a major Health Physics and Radwaste Chemistry problem. j Test Alternative & Frequency: Valve will be exercised (Full Stroke) to the position required to fulfill its function and stroke time during Cold Shutdown. i f j
- 06/29/96- CN-NI-17 Rev.23' Page1of I
< Section 6.1
.- ., _ ..- ., . . . - - . - .~ . -
i i
- -~
l Cctawb2 Units 1 and 2.- 1
.l 4
i
;p-j i i
i 4~ l Justification for Deferral 1
- Item Number: CN-NI Valve: IN1332A, INI333B -
2N1332A,2NI333B 1 I Flow Diagram: CN 1562-1.2 2 CN 25621.2 Code Category: B ) ASME Class: 2 i Function: Aligns suction of centrifugal charging pumps to the refueling water j storage tank (FWST). !_ Test Requirement: Exercise valve (full stroke) to the position required to fulfill its y function and stroke time every 3 months. Basis for Deferral: If one of these valves were to fail in the open position during testing,
- the FWST would be aligned to the suction of the charging pumps. 1 l
This could result in an increase in RCS Boron inventory and could result in plant shutdown. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill ! its safety function and stroke timed during cold shutdown. v \ i I. i i-a i r l O 06/29/96 CN-NI-18
' Rev. 23.. Page1of I l Section 6.1
'l CctawbiUnits 1 and 2 i
\
i i Justification for Deferral i Item Number: CN-NI-19 s
- Valve: INIl36B
{ 2 nil 36B
- Flow Diagram:. CN-1562-1.2 -
CN-2562-1.2 i Code Category: B . ~ ASME Class: 2 ! Function: Valve is opened for the recirculation phase of ECCS operation to allow i flow from the residual heat removal pumps to the safety injection l i pumps. 1
- f Test Requirement
- Exercise valve (Full Stroke) to the position required to fulfill its j- function and stroke time every three months.
Basis for Deferral: Based on Design Engineering evaluation, opening this valve during power operation could degrade ND system flow in the event of a Large Break LOCA. i [ Test Alternative & Frequency: Valve will be exercised (Full Stroke) to the position required to fulfill its function and stroke timed during cold shutdown.
- j l
i 4 i O 06/29/96 CN-NI-19 Rev.23 Page1 of 1 , SectiJ f. 6 i ,
1 Cct:wb2 U:its 1 cnd 2 1 D 5 1 Justification for Deferral 1 Item Number: CN NI 20
; Valve: IN1342
- 2NI342 Flow Diegram CN-1562-1.2 CN-2562-1.2 Code Category
- C i ASME Class: 2 l Function: Opens to provide suction to the safety injection pumps from residual ;
heat removr.i pump (IB) (2B) discharge during the recirculation phase ! following safety injection actuation. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. Basis for Deferral: Valve cannot be full stoke exercised during power operation since the only full flow flowpath discharges into the Reactor Coolant system. I Safety injection pump discharge pressure (approximately 1520 psig) ! cannot overcome Reactor Coolant System pressure. Valve cannot be full stroke exercised during cold shutdown since this l could result in a cold overpressunzation of the Reactor Coolant l System. ) ' l Valve cannot be partial stroke exercised during power operation since i the valve lineup would require opening (INil; 5B) (2 nil 36B). If an l accident would occur with (INil36B) (2 nil 36B) open, injection flow 1 would be diverted from both trains of the ND system. 4 Test Alternative & Frequency: Exercise check valve (partial stroke) to the position required to fulfill its function at cold shutdown. Exercise check valve (full stroke) to the position required to fulfi:i its function at refueling.
- 06/29/96 CN NI 20 Rev.23 Page1of I r Section 6.1
i Catawba Units 1 and 2 q i Justification for Deferral
~ ; Item Number: CN-NI 21 Valve: INil21A, INil52B 2 nil 21 A, 2 Nil 52B l
Flow Diagram: CN-1562-1.2 CN 25621.2 i Code Category; B l ASME Class: 2 ) Function: Valves 1(2) Nil 21A and 1(2) Nil 52B are motor operated gate valves on the discharge side of N1 Pump A and B to NC Imops B&C and A&D, J respectively. The valves are normally closed during the injection phase and l O cold leg recirculation phases of ECCS operation to prevent diversion of flow via the NC hot legs. 1 i Test Requirement: Exercise valve full-stroke to position required to fulfill its function and stroke i time every three months per Oma-1988 Part 10,4.2.1.1. l Basis for Deferral: Exercising the valves in modes 1-3 can result in challenging NI pump discharge relief valves and overpressurization of NI piping due to reactor coolant leakage pressurizing piping downstream i Alternate Testing & Frequency: These valves will be exercised (full-stroked) to position to fulfill its function j and stroke timed during cold shutdown. i O v 06/29/96 CN-NI 21 Rev.23 Page1ofI
1 Cctr.wb2 Units I c:d 2 1
. m I
j i T i e Justification for Deferral i i Item Number: CN-NI 22 Valve: INIl44A, 2 Nil 44A i 1 I Flow Diagram: CN-1562-1.2 i CN-2562-1.2 1 l i j Code Category: B i: ASME Class: 2 Function: Valves nil 44A are motor operated valves on the NI Pump B miniflow 3 line. The valves are open during the injection mode when the NI , l l Pumps are operating. During the recirculation mode, when the NI 1 P Pumps are taking suction from the containment sump (via the ND System), the valves are closed to isolate the miniflow line. Closure of
\.
the valves prevems the possibility of introducing reactor coolant water into the FWST and diversion of flow from the NC System. The valves are also interlocked with valves, ND28A & nil 36B such that they can i not be opened unless valves, ND28A and nil 36B are closed. ' Exercise valve full-stroke to position required to fulftli its function and Test Requirement:
- stroke time every three months per OMa 1988 Part 10,4.2.1.1.
! Basis for Deferral: If nil 44A was closed for testing and of a loss of offsite power with l the loss of Train A diesel generator as the single failure occured, the ; valve could not be reopened which would result in a loss of both NI Pumps. Test Alternative & Frequency: These valves will be exercised (full-stroked) to position to fulfill its ; function during cold shutdown. L
- 06/29/96 CN-NI 22 Rev.23. Page1 of 1
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I Catawb2 Units 1 cod 2 i > i -Od 4 i L i'
- Justification for Deferral
) - ! tem Number: ' CN-NI-23 { . I ' Valve: IN1334B, 2N1334B - 1 i j Flow Diagram. CN-1562 1.2 j CN 2562-1.2 1 Code Category: B ASME Class- 2 i Function:' Provides flowpath from B Train of Residual Heat Removal td B Train
- of Chemical and Volume Control, and from A Train of Residual Heat i Removal to A Train of Lafety Injection.
i Test Requirement: Stroke time test in accordance with Oma-1988 Part 10,4.2.1.1. { \ Basis for Deferral: Closing this valve during power operation degrades both trains of Safety Injection. With the single failure of Train B diesel generator, l Train A of Safety Injection, which is provided suction from Residual Heat Removal via NI334B or Nil 36B, would be inoperable (since nil 36B is normally closed). Train B of Safety Injection would already , be inoperable due to the single failure.
- Test Alternative & Frequency: Valve will be cycled and stroke timed tested during cold shutdown.
l i i i
?
4 i e % J 06/29/96 CN-NI-23 Rev.23 .Page1 of 1 Section 6.1 t
Cet;wba U:its I cnd 2 d a O . Justification for Deferral Item Number; CN-NS 01 Valve: INS 004, INS 021, INSO98, INSO99 2NS004,2NS021,2NSO98,2NSO99 Flow Diagram CN-1563 1.0
- CN-2563 1.0 Code Category: C .-
ASME Class: '2 Function: Vilves open to provide flow from the refueling water storage tank to the spray headers. l Test Requirement: Exerc; e check valve (full stroke) to the position required to fulfill its ) I function sery 3 months. b Basis for Deferral: These valves camua 9 full stroke exercised since the only full flow flowpath is to the spray headers which would result in spraying containment. Test Alternative & Frequency: Valves will be exercised (partial stroke) to the position required to l fulfillits function every 3 months. ( 1(2)NS004 and 1(2)NS021 will be alternately disassembled and the disk will be mechanically exercised each refueling. Should the valve fail to stroke acceptably, the other valve will be also disassembled. 1(2)NSO98 and 1(2)NSO99 will be alternately disassembled and the disk will be mechanically exercised each refueling. Should the valve fail to stroke acceptably, the other valve will be also disassembled. I 1 ( 06/29/% . CN NS-01 l
.Rev.23 Page1of 1 Section 6.1
Cetawb2 Ugits 1 and 2 A
't I V
1- Justification for Deferral 4
. Item Number: CN-NS-02 l . .
Wive: INS 013, INS 016, INS 030, INS 033, INSO41, INSO46 4 2NSO 13, 2NS016, 2NS030, 2NS033, 2NSO41, 2NS046 Flow Diagram: CN 1563-1.0 CN-2563-1.0 ~ 1 i ! Code Category: C ASME Class: 2 1 I' Function: Opens to flow from the containment spray and residual heat removal l pumps to the containment spray headers. I Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its ! s function every 3 months. I
} Basis for Deferral: To full or partial stroke these valves flow from the containment spray or residual heat removal pumps would have to be initiated. Tids I would result in spraying water through the spray nozzles into containment i
Test Alternative & Frequency: During each refueling one of the six check valves will be disassembled and the disk will be mechanically exercised. The next refueling a 1 different valve in this group will be disassembled and so on, such that all six valves will be tested within a six refueling time period. Should
- any one valve fail to stroke acceptably, the remaining five valves will also be disassembled.
4 1 4 C. ). 06/29/96 CN-NS-02 l Rey,23 Page1of I ! Section 6.1
Cct:wba Units 1 and 2 Q NJ Justification for Deferral item Number: CN-NS 03 Valve: INS 038B, INSO43A 2NS038B, 2NSO43A Flow Diagram: CN 15631.0 ' CN-2563 1.0 Code Category: B ASME Class: 2 Function: Residual Heat Pump A (and B) to Containment Spray Header Containment isolation Valve. Test Requirement: Stroke time test in accordance with Oma 1988, Part 10,4.1.1.1. Basis for Deferral: If an accident occurred with one of these valves open, injection flow would be diverted from both trains of the ND System. Test Alternative & Frequency: Valves 1(2)NS038B and 1(2)NS043A will be tested during Cold Shutdown. 4 J i 1 4 b 06/29/96. CN-NS-03 Rev.23 Page1of 1 Section 6.1
1 Catawb2 Units 1 cad 2
)
i a Justification for Deferral Item Number: CN-NV-01
, l Valve: INV015B l 2NV015B l 1
4 , Flow Diagram: CN-1554 1.0 ; 3 CN 2554-1.0 , }. ! l Code Category: A l ASME Class: 2 Function: Valves closes to isolate flow to the letdown heat exchanger. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its
- function and stroke time every 3 months.
j Basis for Deferral: Failure of this valve in the closed position during testing would result
- in loss of pressurizer level control and could result in plant shutdown.
Test Alternative & Frequency: Valve will be exercise (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. 1, t 4 V 06/29/96 CN-NV-01
.Rev.23 Page1of I Section 6.1
Cct:wba Units 1 cid 2 C
\
Justification for Deferral item Number: CN NV-02 Valve: INV089A, INV091B , 2NV089A,2NV091B Flow Diagram: CN 1554-1.0 CN-2554-1.0 Code Category: B ASME Class: 2 Function: These valves isolate the return flow path from the reactor coolant pump seal water supply. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function and stroke time every 3 months. q Basis for Deferral: Closure of one of these valves during power operation would inhibit seal water flow across the reactor coolant pump seals. This would result in damage to the pump seals. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. 3 I l {J
\
06/29/96 : CN-NV-02 . Rev.23 Page1of 1 Section 6.1
' Cctawb2 Units I c:d 2 U-s Justification for Deferral
, Item Number. CN-NV-03 Valve: INV188A, INV189B 2NV188A,2NV189B Flow Diagram: CN-1554 1.1 CN 2554-1.1 Code Category: B > ASME Class: 2 a . Function: Valves close to isolate the volume control tank (normal charging - supply) upon receipt of a safety injection signal. I Test Requirement: Exercise valve (full stroke) to the position required to fulfill itsfunction O and stroke time every 3 months. O Basis for Deferral: Closure of one of these valves during nonnal unit operation would l isolate the normal suction for the charging pumps. Alternate suction j paths would result in increasing the reactor coolant system boron inventory and could result in plant shutdown. In addition, seal water for the reactor coolant pumps would inhibited. This may result in j l damage to the reactor coolant pump seals. l l Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill l its function and stroke timed during cold shutdon. l i j J O 06/29/96 CN-NV 03 i Rev.23 Page1 of 1 Section 6.1 l
l l. Cctanba Units 1 and 2 f l Q)- 4 Justification for Deferral item Number: CN-NV-04 Valve: INV312A, INV314B 2NV312A,2NV314B l Flow Diagram: CN-1554 1.2 CN 2554-1.2 Code Category: B ASME Class: 2 Function: Valves close to isolate the charging line to the Reactor Coolant System upon receipt of a safety injection signal. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its ! function and stroke time every 3 months. Basis for Deferral: Closure of one of these valves during power operation would isolate ; charging flow to the Reactor Coolant System. This could result in loss of pressurizer level control and cause plant shutdown. j l Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown i O 06/29/96 CN NV-04 Rev. 23 - Page1of I Section 6.1 i i
. _ _ - . _ _ - - - - - - ~ ~ - ~ . _ _ . - - - _ _ _ . . - - -- - v
Cct:wks Units 1 cad 2 fn (.) s Justification for Deferral i. } Item Number: CN-NV-05 Valve: INV254 2NV254 ! Flow Diagram: CN-1554-1.7 CN-2554 1.7 Code Category: C ASME Class: 2 i Function: Valve opens on flow from the refueling water storage tank to suction of the centrifugal charging pumps. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. 2 ( Basis for Deferral: Valve cannot be full or partial stroke exercised during power operation as this would increase the reactor coolant system boron inventory and 4 possibly cause plant shutdown. This valve cannot be full stroke exercised during cold shutdown since this could result in a cold overpressurization of the reactor coolant system. Test Alternative & Frequency: Exercise check valve (partial stroke) to the position required to fulfill its function at cold shutdown. Exercise check valve (full stroke) to the , position required to fulfill its function at refueling. N M d
- 06/29/96 ' CN NV-05 Rev.23 Page1of I Section 6.1 f
l
- Cctr.wbn Units I cad 2 ~ ,
Justincation for Deferral e f l
- . Item Number
- CN-NY l Valve: INV270, INV290 q 2NV270,2NV290 g- .
l Flow Diagram- CN 1554-1.7 CN 2554-1.7 3 .. j Code Category:. C ASME Class: 2-i. 4
. Function: Open to provide flow from the centrifugal charging pumps to the nomial charging line or Cold Leg injection Header.
Test Requirem<:nt: Exercise check valve (full stroke) to the position required to fulfill its j x- function every 3 months. , l 1 Basis for Deferral: . Valves cannot be full stroke exercised during power operation. The only full flow flowpath is through the Cold Leg injection Header into the reactor coolant system. .'this would cause an increase in reactor coolant system boron inventory and possibly cause plant shutdown. [... Valves cannot be full stroke exercised during cold shutdown since this could result in a cold overpressurization of the reactor coolant system. Test Altemative & Frequency: Exercise check valve (partial stroke) to the position required to fulfill its function every 3 months. Exercise check valve (full stroke) to the j- position required to fulfill its function at refueling. 4 k' d i. I 4 f- ~ 06/29/96 CN-NV-06 h Rev.23 . Page1of 1 i Section 6.1
. . - . - - ~ . . . . . . -.. . _ - . . . - - . - . ... -- - -
Cctrwba Units I c d 2
/
4 4
! i 1
I Justification for Deferral 1 4 {- . .
! . Item Number: CN-NV-07.
j . ~ Valve: INV202B, INV203A 5 2NV202B,2NV203A , I~ Flow Diagram: CN-1554-1.6 ! CN-2554-1.6 4
- i. -
3
, Code Category: B 1 .
. ASME Class: 2-
- Function
- Valves can be closed to isolate the centrifugal charging pump miniflow line during cold leg injection phase following a LOCA.
Test Requirement: Exercise valve (full stroke) to the position required to fulfill its
- function and stroke time every 3 months.
Basis for Deferral: Failure of one of these valves in the closed position during test would
- - isolate the centrifugal charging pumps miniflow line. This path must
.. remain open in the event of a LOCA until the operator verifies a L primary side break at which time the valves are closed. In the event of a secondary side break, the miniflow path must remain open in order - to prevent possible dead heading and damaging the centrifugal { charging pumps. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. i ( i: 1 06/29/96 - CN-NV-07 Rev.23. Page1of 1 j- Section 6.1
Cctawba Units i n:d 2 (Y
%)
Justification for Deferral Item Number: CN-NV 08 Valve: INV813 ! 2NV813 4 Flow Diagram: CN 1554-1.7 CN-2554-1.7 , Code Category: C l ASME Class: 2 Function: Opens to provide suction to the centrifugal charging pumps from residual heat removal pump discharge during the recirculation phase following safety injection actuation. O V~ Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. f Basis ~for Deferral: Valve cannot be full stroke exercised during power operation since the only full flow flowpath discharges into the Reactor Coolant System. This would cause an increase in Reactor Coolant System boron inventory and possibly cause plant shutdown. Valve cannot be partial stroke exercised during power operation. Use of the partial stroke flowpath (through the miniflow line to the seal water heat exchanger) i would: 1) Cause an increase in the boron concentration in the volume control tank which is the normal source of makeup water for the positive displacement charging pump. This would cause an increase in the Reactor Coolant System boron inventory and possibly cause i plant shutdown. 2) Cause the return path for the reactor coolant
- pump seal water to be deadheaded due to the miniflow path pressure.
This would result in loss of cooling to the seals and cause possible , l pump damage. Valve cannot be full stroke exercised during cold j l - shutdown since this could result in a low temperature ! overpressurization of the Reactor Coolant System. j I Test Alternative & Frequency: Exercise check valve (partial stroke) to the position required to fulfill . its function during cold shutdown and exercise check valve (full ! stroke) to the position required to fulfill its function during refueling. l l 06/29/96 CN NV-08 Rev.23- Page1of 1 Section 6.1
_ . ~ . . - _ . _ _ _ _ _ . _ _ _ _ _ _ . . _ _ _ . ._ . . - . _ . _ . Cetztbn Uzits 1 and 2
-(
4 Justification for Deferral-1 4 4 Item Number; CN NV-09
' INV874 Valve:
2NV874 i Flow Diagram: CN 1554-1.8 CN-2554-1.8
- - . Code Category
- A, C
} i ASME Class: 2
- Function
- Provides containmentisolation.
Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. j Basis for Deferral: System design does not provide any indication for verifying valve closure upon flow reversal. Test Alternative & Frequency: Verify valve closure during performance of leak rate test during refueling. l. i z e i' 06/29/96 CN NV-09 Rev.23 Page1 of 1 Section 6.1 e e- w- v- 1m u --T- r
. . = - - - - _ - . .-- - -
Cctawba U its I c:d 2 bh Justification for Deferral i Item Number: CN NV-10 Valve: INV252A,'1NV253B
. 2NV252A,2NV253B Flow Diagram: CN 1554-1.7 CN 2554-1.7 Code Category: B ASME Class: 2 Function: Aligns refueling water storage tank (FWST) to the suction of the centrifugal charging pumps upon receipt of a safety injection signal. ;
i
- Test Requirement: Exercise valve (full stroke) to the position required to fulfill its )
function and stroke time every 3 months. l j Basis for Deferral: If one of these valves were to fail in the open position during testing, . the FWST would be aligned to the suction of the charging pumps. I This would result in an increase in RCS Boron inventory and could result in a plant shutdown. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. i 1 j l O 06/29/96 CN NV-10 Rev.23 Page1of I Section 6.1
am4@ % han b = <%_ J Ar -- J 4- 4 5i.,4.a s2 a .A e _ ..---.*.A u _ IiAa>.i M - 4 , Cat wba' Units 1 a::d 2 l b) v Justification for Deferral 1
! Item Number: CN-NV 11 4
- Valve
- INV010A, INVoll A, INV013A 2NV010A,2NV011A,2NV013A 1
I Flow Diagram: CN-15541.0 CN 2554-1.0 i Code Category: B
. ASME Class: 2 Function: These valves must automatically close to isolate containment upon receipt of l
i a Pressurtzer Im 1.4 vel signal, if either valve 1(2)NV001 A or 1(2)NV002A closes, upon receipt of a Phase A Containment Isolation Signal (ST), or on a concurrent failure of the PD pump and both centrifugal charging pumps. These valves are cross-interlocked with valves 1(2)NV001A and 3 1(2)NV002A such that they will automatically close if either 1(2)NV001 A or j 1(2)NV002A is not in the "Open" position. These valves can be operated ,
; from the Auxiliary Shutdown Panel, and cannot be opened unless valves )
1(2)NV001 A and 1(2)NV002A are both open. l Test Requirement: Stroke time and observe fail-safe operation every three (3) months. Basis for Deferral: Letdown header relief valve 1(2)NV014 has experienced liAing and ! subsequent seat leakage as a result of pressure transients during orifice swaps for stroke time testing of valves 1(2)NV010A, 1(2)NV0ll A, and l 1(2)NV013A. leakage past 1(2)NV014 is considered Reactor Coolant (NC) ! system leakage. This leakage directly impacts Technical Specification 3.4.6.2. < Based on the above, testing of these valves is impractical and non-conarvative during power operation. l Test Alternative & Frequency: Valves 1(2)NV010A,1(2)NV0llA, and 1(2)NV013 will be stroke time 4 tested and fail-safe operation verified during cold shutdown. 06/29/96 CN NV-11 Rev.23 Page1of 1 ) Section 6.1 I
Cet:wba Units I and 2 . A l b l Justification for Deferral 4 s item Number: CN NV-12 Valve: INV001A, INV002A 2NV001 A,2NV002A Flow Diagram: CN-1554 1.0 CN-2554-1.0 Code Category: B I ASME Class: 1 Functioni Valves closes to isolate flow to the letdown heat exchanger. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function, observe fail-safe operation, and stroke time every 3 months. Basis for Deferral: Failure of this valve in the closed position during testing would result in loss of pressurizer level control and could result in plant shutdown. Test Alternative & Frequency: Valve will be exercise (full stroke) to the position required to fulfill its function, fail-safe operation verified, and stroke timed during cold shutdown. 1 1 l l I (
' 06/29/96 CN NV-12 Rev. 23 Page1of 1 Section 6.1
)
Crt:wbs Units 1 and 2 J G '
;' d r ,
Justification for Deferral i l Item Number: CN-NW-01 1 Valve: INWOO6, INWO63
- . 2NW006,2NWO63 s
Flow Diagram: CN-1569 1.0 CN 2569-1.0 Code Category: C ASME Class: 2 Function: Open to provide flow from Nuclear Service Water System to the containment valve injection water surge chambers. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its i 7 function every 3 months. Basis for Deferral: Operating these valves would result in placing raw water in the NW l System. i Test Alternative & Frequency: Exercise check valve (full stroke) to the position required to fulfill its function at refueling (NW surge chamber can be drained and isolated at - this time.) ( t 4
-V 06/29/96 CN-NW-01 Rev.23 Page1 of 1 4
Section 6.1
l Catawba Uzits I c d 2 O Justification for Deferral Item Number: CN-NW-02 Valve: INW017, INWO21, INWO24, INWO27, INWO37, INWO40, INWO43, INWO47, INWO50, INWO53, INWO70, INWO74, INWO77, INWO80, ' INWO83, INWO86, INWO89, INWO92, INWO95, INWO98, INW101, INW107, INW109, INW111, INW114, INW120, INW121 through INW136, INW138, INW139, INW140, INW141, INW147, INW148, INW159, INW160, INW163, INW164, INW168, INW169, INW171, INW172, INW178, INW179, INW183, INW184, INW188, INW189, INW193, INW194, INWi%, INW197, INW201, INW202, INW205, INW206, INW209, INW210, INW213, INW214, INW218, INW219, INW223, INW224, INW230, INW231, INW235, INW236, INW240, INW241, INW245, INW246 2NW017, 2NWO21, 2NWO24, 2NWO27, 2NWO37, 2NWO40, 2NWO43, 2NWO47, 2NWO50, 2NWO70, 2NWO74, 2NWO77, 2NWO80, 2NWO86,
/^ 2NWO89, 2NWO92, 2NWO95, 2NWO98, 2NW 101, 2NW107, 2NW109, 2NWl11,2NW114,2NW120,2NW121,2NW123 through 2NW133, 2NW135, 2NW136, 2NW138, 2NW 139, 2NW140, 2NW141, 2NW147, 2NW 148, 2NW 159, 2NW 160, 2NW 163, 2NW 164, 2NW 168, 2NW 169, 2NW171, 2NW 172, 2NW 178, 2NW179, 2NW183, 2NW184, 2NW188, 2NW 189, 2NW 193, 2NW194, 2NW 196, 2NW197, 2NW201, 2NW202, 2NW205, 2NW206, 2NW209, 2NW210, 2NW213, 2NW214, 2NW218, 2NW219, 2NW223, 2NW224, 2NW230, 2NW231, 2NW235, 2NW236, 2NW240,2NW241,2NW245,2NW246 !
Flow Diagram: CN-1569-1.0 CN-2569 1.0 Code Category: C ASME Class: 2 Function: These valves open to supply containment valve injection water to !' certain containment isolation valves. Valves close to prevent system backleakageinto NW System. 1- Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its functions every 3 months. 06/29/96 ' CN-NW-02 Rev.23 Page 1 of 2 Section 6.1
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Justificatir.. for Delegal Item Number: CN-NW-02 (Continued) - Basis for Deferral: Normal plant conditions will not allow these check valves to operate since the valves fed by the NW System are in systems which are normally pressurned with flow passing through them. To operate the check valves normal system pressures would have to be bled offin order to allow NW pressure to open the check valves. This ' is not possible during normal plant operation. Also to stroke valves closed requires Tech. Spec. action statements and containment entry. Test Alternative & Frequency: Valves will be full stroked open each refueling outage. One third of valves will be reverse flow tested each refueling outage with all velves tested over a three outage period. (Generic letter 89 04 response). i-4 i l i i
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06/29/% CN NW-02 Rey, 23 Page 2 of 2 f Section 6.1
C:tawb: U:its 1 c d 2 - h Justification for Deferral i
'- Item Number: CN-RF-01 Valve: 1RF392, IRF448 2RF392,2RF448 Flow Diagram: CN-1599 2.2 CN-2599-2.2 i
Code Category: A, C ASME Class: 2 Function: Provides containment isolation. TestRequirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months.
- Basis for Deferral
- System design does not provide any indication for verifying valve
; closure upon 110w reversal.
Test Alternative & Frequency: Verify valve closure during performance of leak rate test during refueling. t 4 i 4 06/29/96 CN-RF-01 Rev.23 Page1 of 1 Section 6.1
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Justification for Deferral i Item Number: CN-RN-01 Valve: 1RN405, IRN438 2RN405,2RN438 Flow Diagram: CN-1574-2.8 CN-2574-2.2 CN-2574-2.7 Code Category: A, C ASME Class: 2 Function: Provides containment isolation 1 I Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. O
'd Basis for Deferral: System design does not provide any indication for verifying valve upon flow reversal.
Test Alternative & Frequency: Verify valve closure during performance of leak rate test during refueling. 4 i I O 06/29/96 CN-RN41 Rev.23- Page1of 1 Section 6.1
Cct:wbn Urits I cad 2 f .i . g% Justification for Deferral Item Number: CN-RN-02 Valve: IRN437B 2RN437B i Flow Diagram CN 1574-2.8 ! CN-2574-2.2 4 i B Code Category: i ASME Class: 2 ) Function: This valve closes on a high-high containment pressure signal to isolate the supply header to lower containment, j Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function and stroke every 3 months. j Basis for Deferral: Failure of this valve in the closed position during testing would result i in loss of nuclear service water flow to the reactor coolant pump motor t coolers. This would result in unit shutdown and possible damage to i the reactor coolant pumps. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. I J a 1 n
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06/29/96 CN-RN-02 Rev.23 Page1of I Section 6.1
C:tawba Units 1 and 2 i O I Justification for Deferral ! l I Item Number: CN-RN-03 Valve: 1RN484A, IRN487B i 2RN484A,2RN487B Flow Diagram: CN 1574 2.2 CN2574-2.1, CN-2574-2,2 Code Category: B ASME Class: 2 4 Function: Valves close on a high-high containment pressure signal to isolate the lower containment return header. 4 Test Requirement: Exercise valves (full stroke) to the position required to fulnll its function and stroke time every 3 months. 1 , \ Basis for Deferral: Failure of one of these valves in the closed position during testing would result in loss of nuclear service water flow to the reactor coolant pump motor coolers. This would result in unit shutdown and possible damage to the reactor coolant pumps. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulnll its function and stroke timed during cold shutdown. 4 O CN-RN-03 06/29/96 Rev.23 Page1 of I Section 6.1
Cctawbs Units I cnd 2 l (3 . V Justification for Deferral Item Number: CN-SA-01 Valve: ISA003, ISA006 2SA003,2SA006 Flow Diagram: CN-15931.1 CN-2593 1,1 Code Category: C ASME Class: 2 Function: Closes to prevent steam flow reversal in the event of a bss of steam generator, Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its p) ( function every 3 months per Oma 1988 Part 10,4.3.2.1. Check valve
- reverse flow test per GL 89-04.
l Dasis for Deferral: System design does not provide any indication for verifying valve position. No means exist to test for valve closure. Test Alternative & Frequency: Verification of ability to prevent reverse flow will be performed during refueling. During each refueling one of the two check valves will be disassembled and the disk will be mechanically exercised. The next refueling the other valve will be disassembled, such that both valves will be tested within a two refueling time period. Should any one valve fail to stroke acceptably, the remaining valve will also be disassembled.
- V 06/29/96 CN-SA-01 Rev.23 Page1of 1 Section 6,1
4 C:t<_wba Units 1 and 2 (O g 1
. Justification for Deferral 4
Item Nuraber: CN-SM 01
, Valve: ISM 001, ISM 003, ISM 005, ISM 007 2SM001,2SM003,2SM005,2SM007 Flow Diagram: CN 1593-1.0
- CN-2593 1.0 Code Category
- B ASME Class: 2 Function: Main steam isolation valves.
Test Requirement: Exercise valve (full stroke) to the position required to fidfill its function, stroke time, and verify fail safe actuation every 3 months. Basis for Deferral: Closure of these valves during power operation could introduce a severe transient in the main steam lines which could cause a unit trip. Test Alternative & Frequency: This valve will be partially stroked at least once per 92 days. In , addition, valve will be exercised (full stroke) to the position required to fulfill its function, stroke timed, and fall safe actuation verified during startup after cold shutdown. l e j A O 06/29/96 CN SM-01 Rev,23 Page1of 1 Section 6.1
l Cctswba Units 1 cad 2 ' i w Justification for Deferral Item Number: CN-VB-01 Valve: IVB-85 i 2VB-85 I Flow Diagram: CN 1605-3.2 l CN-2605-3.2 { l Code Category: A, C ! ASME Class: 2 l Function:' Provides containment isolation. 1 Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its , function every 3 months. .I Basis for Deferral: System design does not provide any indication for verifying valve closure upon flow reversal. Test Alternative & Frequency: Verify valve closure during performance of leak rate test during
- - refueling.
4 i i 1 E f f f 1
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i O 06/29/96' CN VB-01 Rev.23- Page1of 1 Section 6.1 f
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t Justification for Deferral i 5 Item Number: CN-VG-01 Valve: IVG015, IVG016, IVG029, IVG030, IVG031, IVG032, IVG059, IVG060, IVG073, IVG074, IVG075, IVG076 - 2VG015, 2VG016, 2VG029, 2VG030, 2VG031, 2VG032,
- 2VG059, 2VG060, 2VG073, 2VG074, 2VG075, 2VG076 Flow Diagram: CN 1609 4.0, CN-1609-4.1 CN-2609-4.0, CN-2609-4.1 Code Category: C ASME Class: 3 ,
s Function: Open to supply starting air to Diesel Generators. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. Basis for Deferral: No method exists of directly verifying valve movement. Failure of one valve to operate will result in increase in start time of diesel generator during performance of monthly Tech Spec Surveillance Requirement 4.8.1.1.2.a.4. Test Alternative & Frequency: Valve will be verified to operate during monthly Tech Spec Diesel l Test (Ff/1/A/4350/02A,B - Diesel Generator A, B Operability Test) (PT/2/A/4350/02A,B - Diesel Generator A, B Operability Test) by verifying dicsci starts within required time. In addition, during 3 i- , cold shutdown, a test will be performed which verifies the diesel is able to start within required time with one starting air tank disabled at a time. The test will be performed twice, first with one bank disabled, then with the opposite bank disabled. l 4 O
. 06/29/96 CN-VG 01
- Rev.23 Page1of 1 Section 6.1
Cct wba U:its 1 crd 2 1
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( . I Just'fication for Deferral Item Number: CN-VG 02 , Valve: IVG025, IVG026, IVG027, IVG028, IVG069, IVG070,1VG071, IVG072 2VG025, 2VG026, 2VG027, 2VG028, 2VG069, 2VG070, 2VG071, 2VG072 Flow Diagram:. CN-1609-4.0, CN-1609-4.1 CN-2609-4.0, CN-2609-4.1 Code Category: B ASME Class: 3 Function: Open to supply starting air to Diesel Generators Test Requirement: Exercise valve (full stroke) to the position required to fulfill its q function and stroke time every 3 months. Verify remoic position indication every 2 years. Basis for Deferral: Valve design does not provide any indication of position. Failure of this valve to perform its required function will result in increase in start time of Diesel Generator during performance of monthly Tech Spec Surveillance Requirement 4.8.1.1.2.a.4. Test Alternative & Frequency: Valves will be verified to operate during monthly Tech Spec Diesel Test (FT/1/A/4250/02A, B - Diesel Generator A, B Operability Test) Test (FT/2/A/4250/02A, B - Diesel Generator A, B Operability Test) by verifying diesel starts within required time, in addition, during cold shutdown a test will be performed which verifies the dicsci is able to start within required time with one starting air bank disabled at a time. The test will be performed twice, first with one bank disabled, then with the opposite bank disabled. f) b 06/29/96 CN-VG-02 Rev.23 Page1of I Section 6.1
4 Cctariba Uzits 1 ced 2 i t 3 s Justification for Deferral-j ltem Number: ' CN-VI 01 3- ' Valve: IV1079 2VIO79 Flow Diagram: CN 16051.4 l CN-2605 1.5 4 Code Category: A, C i 4
' ASME Class: 2 I Function: Provides containment isolation i Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months.
l Basis far Deferral: System design does not provide any indication for verifying valve closure upon flow reversal. i Test Alternative & Frequency: Verify valve closure during performance of leak rate test during l refueling. ] t l . 1 a 4 4 i i i 0
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.- 06/29/96 CN-VI-01 Rev.23 Page1of I Section 6.1
1 l Cct:wba Units 1 crd 2 m : l
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Justification for Deferral Item Number: CN-VI42 Valve: IV1077B 2VIO77B Flow Diagram CN 1605-1.4 CN-2605-1.5 Code Category: A t ASME Class: 2 Function: Provides containment isolation. Closes upon receipt of a containment high-high pressure signal. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its . function and stroke time every 3 months. l d Failure of this valve in the closed position during testing would result Basis for Deferral: in loss of instrument air supply to valves and controls within . containment. This would result in loss of normal reactor coolant letdown, containment ventilation unit controls, normal air rapply to the power operated relief valves, etc., thereby possibly causing unit shutdown. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. t l 4 i-a 1 r A 06/29/96 CN-VI.02 Rev.23 Page1of 1 Section 6.1
Cct wb2 Units I ccd 2 (~h O Justification for Deferral item Number: CN-VI-03 Valve: IVI367, IVI368 ' 2VI367,2VD68 Flow Diagram: CN 16051.14 CN-2605-1.5 Code Category: C ASME Class: Function: Close to prevent reverse flow of nitrogen from cold leg accumulator when supplying PORV's from safety air source 1 Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. Basis for Deferral: System design does not provide any indication for verifying valve closure upon flow reversal. Test Alternative & Frequency: Verify valve closure during cold shutdown by stroking the PORV's using the safety air source. i i 06/29/96 CN-VI-03 Rev.23 Page1 of 1 j Section 6.1 i
Cctawb2 Units 1 and 2 I O x /. . I Justification for Deferral l Item Number: CN-VI-04 Valve: IVI369, IVI370 2VI369,2V137(, 1 Flow Diagram: CN-1605 1.14 - CN-2605-1,5 - Code Category: C ASME Class: Function: Open to provide flowpath for nitrogen from cold leg accumulator when supplying PORV's from safety air source Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. Basis for Defenal: System design does not provide any indication for verifying valve operationwhenpassing flow. Test Alternative & Frequency: Verify proper valve operation during cold shutdown by stroking the PORV's using the safety air source. i i i e I 1 l O 1 Q) 06/29/96 CN-VI-04 !
- Rev.23 Page1of 1 i
Section 6.1 l
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Ctt:wbn U:lts 1 crd 2 -(/ Justification for Deferrai 1 Item Number: CN VS-01 Valve: IVS056 2VS056 f l I Flow Diagram: CN 1605 2.1 j ( Code Category: A, C ASME Class: 2 l 1 Function: Prmides containment isolation. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function ever 3 months. Basis for Deferral: System design does not provide any indication for verifying valve closure upon flow reversal. Test Alternative & Frequency: Verify valve closure during performance of leak rate test during refueling. l i l 1
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l 06/29/96 CN-VS411 1 Rev.23 Page1of I l Section 6.1
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4 Cctawba Units 1 and 2 i - G
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J Justification for Deferral item Number: CN-W-01 Valve: I W 016 - 2 W 016 i f Flow Diagram: CN 1559-1.0 CN-2559-1.0 Code Category: A, C i ASME Class: 2 3 Function: Provides containmentisolation. l-Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its l function every 3 months. ,( Basis for Deferral: System design does not provide any indication for verifying valve closure upon flow reversal. Test Alternative & Frequency: Verify valve closure during performance of leak rate test during refueling. i i i l i i 1 1 4 l 06/29/% CN-W-01 I Rev.23 Page1of 1 l 1 Section 6.1 i
Cct:wba Usits I c:d 2 A 1 l Justification for Deferral l Item Number: CN-YM 01 Valve: ' lYM121. 2YM121 Flow Diagram: CN-1601 3.1 CN 1601-3.1 Code Category: A, C ASME Class: 2 I Function: Provides containment isolation. Test Requirement: Exercise check valve (full stroke) to the position required to fulfill its function every 3 months. )
. Basis for Deferral: System design does not provide any indication for verifying valve closure upon flow reversal.
Test Alternative & Frequency: Verify valve closure during performance of leak rate te::t during refueling. i 06/29/96 CN-YM-01 l
'Rev.23- Page1of I Section 6.1}}